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MICHIGAN STATE UNIVERSITY
RADIATION SAFETY MANUAL
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NOTICE TO RADIOACTIVE MATERIALS USERS
The Radiation Safety Manual and further radiation safety information can be found or viewed at the following locations: •Principal investigator •Department safety representative •ORCBS WWW Home Page http://www.orcbs.msu.edu See Radiation Safety
•ORCBS 355-0153
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Preface.....................................................................................3 The The Mic Michi higa gan n Sta State te Univ Univer ersi sity ty Broa Broad d Sco Scope pe Lice Licens nse. e. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. . 3 The Radiation Safety Committee ... ... ... ... ... .. ... ... .. ... ... .. ... ... .. ... ... .. ... ... 4 Appr Approv oval alss for for Use of Radi Radioa oact ctiive Mate Materrials ials .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. 4 Resp Respon onsi sibi billitie itiess of the the Pri Princ ncip ipal al Inv Inves esttigat igator or .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. . 5 Responsibilities Responsibilities of the Worker.................. Worker............................... ........................... ........................... ............. 6 Sanctions for Non-Compliance.........................................................7 Training....................................................................................9 Ionizing Radiation Theory...............................................................10 Radioactive Decay... .... .... .... .... .... .... .... .... .... .... .... .... .... .... .... 10 Radiation Units..................................................................11 Biological Effects of Radiati ation ... ... ... ... ... .. ... .. ... ... .. ... ... .. ... ... .. ... ... .. ... 13 Tiss Tissue ue and and Cel Celll Sen Sensi siti tivi vity ty to Radi Radiat atio ion n .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. 13 External and Internal Radiation Exposures...................................14 Laws Laws and and Regu Regula lattions ions Co Conc ncer erni ning ng Rad Radia iati tion.. on.. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. . 15 ALARA.......... ........... ........... ........... ........... ............ ......... 16 Maximum Per Permissible Exp Exposur osuree .. ... ... .. ... ... .. ... ... .. ... ... .. ... ... .. ... . 16 Personnel Monitoring.. .... .... .... .... .... .... .... .... .... .... .... .... .... .... . 18 Minors Working with Radioactive Material..................................19 Pregnant Radiation Workers...................................................19 Expo Exposu sure re Limi Limitts for for the the Gene Generral Publ Public ic .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. 19 Area Restrictions .... .... .... .... .... .... .... .... .... .... .... .... .... .... .... .... 20 Labeling Requirements .... .... .... .... .... .... .... .... .... .... .... .... .... .... . 21 Bioassays........................... Bioassays.................................................. ..............................................22 .......................22 Ordering Radioactive Materials................................................22 Rece Receiv ivin ing g and Moni Monito tori ring ng Radi Radioi oiso soto tope pe Ship Shipme ment ntss .. .. .. .. .. .. .. .. .. .. .. .. 22 Tran Transsfer of Radi Radioa oact ctiive Mater ateriials als .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. . 22 Food and Drink Policy.......................................................... Policy.......................................................... 23 Security of Radioactive Materials.............................................. Materials.............................................. 23 Inven nvento torry of Radi adioact oactiive Mat Materi erials.. als.. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. 24 Shi Shipmen pmentt of Radi Radio oacti active ve Mat Materi erials als .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. 24 Terminating Employment.......................................................24 Leak eak Test ests of Seal ealed Sour Sourcces.... ... ... ... ... ... .. ... ... .. ... ... .. ... ... .. ... .. 25 Radi Radiat atio ion n Safe Safety ty for for Mac Machi hine ne Pro Produ duce ced d Radi Radiat atio ion n .. .. .. .. .. .. .. .. .. .. .. .. .. 25 Princi ncipal In Inves vestigator ator Abs Absenc ences ... ... ... ... ... .. ... ... .. ... ... .. ... ... .. ... ... 25 Radiation Laboratories.... .... .... .... .... .... .... .... .... .... .... ....title .... .... ... 26 Sign.... up.... to vote on this Laboratory Design and and Equipment ... .. ... ... ..Useful ... ... .. ... ...Not .. ...useful ... .. ... ... . 26 Clean Laboratory Conditions and Containment......................... Containment.............................. ..... 26 Unattended Operations..........................................................27 Monitoring Instruments.........................................................28
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APPENDICES
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Application For Approval .... .... .... .... .... .... .... .... .... .... .... .... .... .... .... ... 39 Carbon-14.......... ........... ........... ........... ........... ............ ........... .... 43 Chromium-51.......... ........... ........... ........... ........... ............ ........... 45 Hydrogen-3 ............ ........... ........... ........... ........... ............ ........... 47 Iodine-125...................... Iodine-125....................................... .................................. .................................. ......................... ........ 49 Phosphorus-32 .......... ........... ........... ............ ........... ........... ......... 51 Phosphorus-33 .......... ........... ........... ............ ........... ........... ......... 53 Sulfur-35..................................................................................54 Dire Direct ctio ions ns for for Con Condu duct ctin ing g a Radi Radiat atio ion n Saf Safet ety y Sur Surve vey y .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. . 56 Iodination Sa Safety Ti Tips .... .... .... .... .... .... .... .... .... .... .... .... .... .... .... .... ... 58 Laboratory Classification Table.........................................................60 PI Training Checklist .... .... .... .... .... .... .... .... .... .... .... .... .... .... .... .... .... 62 Poin Pointe terrs for for Hand Handlling ing Radi Radioa oact ctiv ivee Was Waste .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. . 64 Preg Pregna nant nt Ra Radia diation Wor Workers Pol Policy... .. ... .. ... ... .. ... ... .. ... ... .. ... ... .. ... ... .. .. 65 Proper Properti ties es and and Expo Exposu sure re Rate Ratess of Some Some Comm Common on Bet Betaa Emit Emitter terss . .. . . . . . . . .. . . . . . . 66 Radiological Units........................................................................67 Radioisotopes Common at MSU.......................................................68 Sec Securi urity and and Sto Storage age of Radi Radio oisoto otopes pes .. ... .. ... ... .. ... ... .. ... ... .. ... ... .. ... ... .. . 69 Surv Survey ey For Form m Used Used By By Mich Michig igan an Sta State te Uni Unive vers rsit ity y .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. . 70 Transporting Instructions for Radioactive Material................................... Material................................... 72 Ref References nces and Other Resou esourrces ... ... ... ... ... .. ... ... .. ... ... .. ... ... .. ... .. ... ... .. . 74 Glossary...................................................................................76
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Preface
In every facility where hazardous materials are utilized, it is necessary to maintain a p document which establishes specific methods and procedures to develop and maintain safet compliance. Safety is the practice practice of a set of rules, guidelines guidelines and procedures which p workers, facilities, facilities, the general general public and the environment. environment. Compliance is the the maintenan procedures, practices, documents and records which demonstrate that federal, state and local and regulations are not compromised. It is a necessary challenge for all administrators, s committee members, faculty, staff, students and workers to maintain safety and complianc laboratory and research facilities, the challenge is accentuated with the myriad of procedure materials utilized, and the continuous change and evolution of these conditions.
This document will serve as a guide to meeting this challenge by defining the structure, po procedures, responsibility and regulatory stance set forth by the U.S. Nuclear Regul Commission (NRC), the State of Michigan, the Michigan State University NRC license Radiation Safety Committee (RSC), and the Office of Radiation, Chemical and Biological S (ORCBS). However, it is important that that all principal investigators investigators and workers remember th burden of daily compliance and safe practices is their own, and that they are the most critical l the maintenance of these goals.
The Office of Radiation, Chemical and Biological Safety gives many thanks to the Univers Michigan Radiation Safety Service team for providing information for the Radioisotope Sheets, to Larry Chapin, Department of Animal Science for the Iodination Emergency Proce to Reginald Ronningen, Cyclotron Physicist and RSC member for the many hours of re discussion and assistance with this document; to the Radiation Safety Committee for their val input and review, and finally, to the Radiation Safety staff at the ORCBS, who did the lion's of the work.
The Michigan State University Broad Scope Licens
Michigan State University operates under the U.S. Nuclear Regulatory Commission Lic Sign up to vote on this Number 21-00021-29. This license is a large scale non-fuel cycle Type A title broad scope lic Usefulhave who a Not Type A broad licenses may only be given to large facilities longuseful history of radioa materials use with a good safety record. It allows Michigan State University the privilege of large varieties of radioactive radioactive materials. Large amounts of activity are are authorized and may th
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The Radiation Safety Committee
The Michigan State University Radiation Safety Committee is comprised of faculty, administr and staff who have been delegated responsibility for radiological health, safety and complia the University. Approval for use of radioactive materials, materials, reviewing policy and campus rad safety, advising the university administration in radiation safety issues and programs, and the operations and activities of the ORCBS Health Physics staff are some of the func performed by the RSC.
Radiation Safety Committee members are appointed by the University administration, accord their experience and skills, which enable them to effectively perform their duties. Radiation S Committee members' qualifications are reviewed by the NRC, then members are named i broad license as being responsible for oversight and review of campus radiation safet Radiation Safety Committee members have expertise in the wide range of uses of radioa materials at Michigan State University. University. Current members of this committee are listed in the telephone directory, which is updated each year.
Approvals for Use of Radioactive Materials
Approval for the use of radioactive materials is given by the Radiation Safety Committee period of one year, and is reviewed annually. Approval may be obtained by submitting a application describing the requested material and quantity to be used, the location, individuals will handle the material, the training and experience of the applicant, the training of worker protective equipment to be used, if any, monitoring equipment, a brief description of experim procedures with emphasis on potential safety concerns, and waste disposal informa Applicants must have faculty status, assistant professor or greater, experienced in the u radioactive materials and must be trained by the ORCBS prior to approval. The application w reviewed by RSC members, wherein approval may be granted.
The RSC may require additional conditions under which the use of the material must be condu The approved principal investigator may then order, receive and use the requested material must do so according to the statements and representations made in the application, and conditions set forth by the safety committee and all applicable local, state Sign up to vote on this titleand federal regulations and license conditions. Violations or infractionsUseful of these conditions Not useful may be cau suspension or termination of the approval to receive and use radioisotopes.
For most applications to use radioactive materials, materials, interim approval may be given by the Rad
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Responsibilities of the Principal Investigator
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Principal investigators are directly responsible for compliance with all regulations gove radiation safety in the laboratory, and for safe practices of individuals working under supervision. Principal investigators are obligated to: 1.
2. 3. 4. 5. 6. 7. 8. 9. 10. 10 . 11. 11 . 12. 13. 13 . 14. 14 .
Ensure Ensure that indivi individuals duals workin working g under their their control control are properly properly supervi supervised sed and train train enable safe working habits and prevent exposures to themselves and others a contamination of the work areas or environment. Inadequate supervision supervision and la training have been cited as indicative of negligence in lawsuits involving radiation. Be aware aware of the potenti potential al radiation radiation hazards hazards inherent inherent in a propose proposed d activity; activity; be be respo for instructing personnel in safe practices or directing personnel to sources of inform concerning safe practices. Maintain Maintain invento inventory ry and knowledge knowledge of the various various forms forms (physical (physical and chemical chemical quantities of radiation which are present in their work areas. Avoid Avoid any unneces unnecessary sary exposu exposure, re, either either to themsel themselves ves or to other other worker workers. s. Understand Understand the the risks risks associated associated with the possessio possession, n, use and shipment shipment of all all radi materials. Federal and state state regulations control the use and shipping shipping of radioa radioa materials and certain other hazardous materials. Keep current current recor records ds of the receip receiptt and the dispos dispositio ition n of radioacti radioactive ve material material in possession including use in research, waste disposal, transfer, storage, etc. Maintain Maintain constant constant surveillance surveillance and immediat immediatee control control of radioacti radioactive ve materials materials to pr unauthorized removal or tampering, and/or assure that all of the workers occupyin area maintain security. Post warni warnings ngs and restr restrict ict entry entry to areas areas that contain contain potent potentiall ially y hazardous hazardous radioact radioact chemicals. Label radioactive use equipment and work areas. Notify Notify the the ORCBS ORCBS of any personn personnel el changes, changes, inclu including ding addit addition ion or termi terminati nati employees, or changes of areas where radioactive materials may be used or stored. Assure Assure instruction instruction of female radiation radiation workers workers of the risks associated associated with working working radioactive materials materials during pregnancy. (NRC Reg. Guide 8.13). Assure Assure designation designation of a responsible individual individual to oversee oversee radioisotope radioisotope work during during absences, and of a stand-in principal investigator with the required committee appr during extended absences (greater than 60 days). Ensure that that radiation radiation safety surveys surveys and audits in in the laboratory laboratory are conducted maintain records for review. Sign up vote thisradioactive title Be aware of regulations regulations and and requirements requirements pertaining pertaining totothe use uson e of radioact ive mate maintain compliance and a safe working area. Useful Not useful Use radioactive radioactive materials materials according to to statements, statements, representations representations and conditions conditions set in the radioactive materials use approval given by the Radiation Safety Comm
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Responsibilities of the Worker
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Individuals who use radioactive materials assume certain responsibilities responsibilities in in their work. individual worker is the "first line of defense" in protection of people and the environment ag undue risks of radiation exposure and/or contamination. Since the workers, themselves, a direct handlers of the radioactive material, the final responsibility lies with them for safety compliance with laws and regulations. regulations. For this reason, it is critical critical that they be aware of the safe practices and requirements for use of radioactive materials.
The term "worker" is used by the university to identify an individual who uses radioactive ma in the course of his/her employment or study with with the university. Workers may be prin investigators, graduate students, undergraduate students, technicians, post-doctorates, visito any other individual who will handle radioactive material. The following items are to be adhe at all times by radiation workers. 1.
Each worker worker must must attend attend the the entire entire ORCBS ORCBS traini training ng class, class, includi including ng radiati radiati chemical safety. Workers are prohibited from handling radioactive materials unti class has been completed. Radiation workers must attend a refresher session each ye
2.
The worker worker must complete complete the the radiation radiation safety safety examinati examination on and pass with a score score of or better. Workers are prohibited from handling radioactive materials until thi occurred.
3.
Workers Workers are are responsi responsible ble for adher adhering ing to all all laws, laws, rules, rules, regulati regulations, ons, license license condit condition ion guidelines pertaining to the use of radioactive materials.
4.
Workers must wear their their assigned assigned radiation radiation dosimeter dosimeter during during uses uses of radioactive radioactive m (See Personnel Monitoring for details on dosimeter requirements.)
5.
Workers Workers must must practice practice ALARA (As Low Low As Reasonably Reasonably Achievable Achievable)) in their work minimize the potential for exposures, contamination or release of radioactive materials
6.
Radiatio Radiation n work areas areas must must be monitore monitored d by the user user after after each use of radio radioacti active ve ma If contamination is found, it must be cleaned up.
7.
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No changes changes in in experimental experimental procedures procedures using using radioact radioactive ive materia materials ls useful are are to occur witho Useful Not approval of the principal investigator. Do not take short cuts. Changes in experim procedures impacting upon safety (higher quantities, higher risk, use in animals, must be approved by the MSU Radiation Safety Committee.
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for notifying the ORCBS of termination of employment and returning the radi dosimeter at the end of their employment. 12. 12 . Workers are responsible responsible for maintaining maintaining security of radioactive radioactive materials. materials. (See sect Security of Radioactive Materials).
Sanctions for Non-Compliance
Following the 1993 U.S. Nuclear Regulatory Commission inspection of MSU, the University directed to design and implement a plan for categorizing and responding to instanc noncompliance with NRC regulations that are identified in the inspections conducted b ORCBS. This consisted consisted of assigning "severity "severity levels" to violations, violations, and levying sanct laboratories found in noncompliance.
During inspections, noncompliance with requirements may be identified. A report is is sent principal investigator following the survey, detailing the results of the inspection, and expla what corrective actions are required within the radioisotope use area. If the problems are corr no further actions will be required. If the problems are not corrected, a Notice of Violation m sent to the principal investigator, and may require further corrective actions and/or documenta
Violations are classified in five severity levels based on NRC definitions. The most sever level I violation, which could result in a researcher losing the privilege to use radioactive ma and the least severe is a level V. If violations are found, actions that may be taken are gea these severity levels. A given instance of noncompliance may result in multiple actions, depe on specific circumstances, whether the incident is an isolated occurrence or is part of a repe pattern, etc.
The severity levels for violations are derived from NRC regulations and from MSU's recent s history. For example, proper labeling of radioisotope radioisotope work and storage areas, stock solution solution waste containers, has been a long-running concern at the University, hence appears as a rela severe level III violation.
The Notice of Violation is also intended to identify severity levels, assign sanctions and docu that instructions instructions were given concerning concerning violations found. found. It is to be reviewed by the prin investigator, signed and placed with the radiation safety records for the laboratory. Sign up to vote on this title
Usefulof 1993. Not useful The sanction system was activated during the last surveyperiod Due to feed-back researchers, changing regulatory issues and experience gained in practice, the system may ch to better reflect the degree of severity severity for violations. This means that additional flexibility flexibility m
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Severity Level III: A serious violation, but does not present immediate risk to health, s
Sheet Music
the environment or the license.
Severity Level IV: A violation, but not serious. Poses little risk to health, safety, environ
or license.
Severity Level V: A minor violation; typically something in lesser technical matters, su
record keeping errors of minor impact. Poses no immediate risk to health, safety, environm license, but is a compliance issue which may lead to increased concerns or is a minor tech violation.
Note: Any violation, when seen repeatedly, may be escalated to a higher severity level. Repeat violations interpreted as a disregard for safety regulations and must be dealt with quickly and effectively to avoid undue r exposure or jeopardization of the NRC broad license.
SANCTION ACTIONS FOR NONCOMPLIANCES IN RADIATION SAFET Implemented November, 1993
Severity
Possible Resulting Action
Level
I-V
Viol Violat atio ions ns note noted d on on ORC ORCBS BS surv survey eyss and and sent sent to PI. PI. All All vio viola lati tion onss hand handle led d thi thi
I -V
Writ Writte ten n corr correc ecti tion onss req requi uire red d of PI and and mai maint ntai aine ned d in lab labor orat ator ory y reco record rd boo books ks for for r
IV, IV, V
Healt Health h phys physici icist st conta contacts cts princi principal pal inves investi tigat gator or and and dis discus cusse sess probl problem( em(s) s) and cor
I -V
Requ Requir iree tha thatt inv invol olve ved d per perssonne onnell at attend tend safet afety y cla class ss agai again. n.
I-V
Increase ORCBS surveillance.
I -V
Increa creassed survei veillance ance requi equirred of of lab labor oraatory ory st staff.
I -V
Lett Letter er to prin princi cipa pall inv inves esti tiga gato torr fr from heal health th phys physic icis ist. t.
I, II
Lette Letterr to princ princip ipal al inves investi tigat gator or from from Radiat Radiation ion Safet Safety y Off Offic icer; er; resp respons onsee is isrequi required red
I-II I-IIII
Plac Placee res restr tric icti tion onss on on ind indiv ivid idua ual( l(s) s) caus causin ing g non non-c -com ompl plia ianc nces es..Not useful Useful
I-II I-IIII
Susp Suspen end d ship shipme ment ntss of radi radioa oact ctiv ivee mate materi rial alss to prin princi cipa pall inve invest stig igat ator or..
I, II II
Re ir
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SEVERITY LEVELS FOR VIOLATIONS FOUND IN RADIATION SAFETY INSPECTIONS
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November, 1993
Severity No .
Compliance Requirement
Level
V
1.
NRC "N "Notice To To Em Employees" an and "L "Licensing an and Re Regulation In Information" a posted.
I - III III
2.
Radi Radioa oact ctiv ivee mat mater eria ials ls are are und under er the the con const stan antt sur surve veil illa lanc ncee and and imme immedi diat atee con con licensee, or otherwise secured to prevent tampering or unauthorized removal.
I - III III
3.
Radi Radiat atio ion n use users rs are are ade adequ quat atel ely y tra train ined ed for for the the funct unctio ions ns perf perfor orme med. d.
I - III
4.
Surveyed areas are free of contamination.
I - IV
5.
Labor aborat ato ory eq equipm uipmen entt is is fu funct nctional onal and and is is us used cor correctl ctly.
III III - V
6.
Labo Labora rato tory ry radi radiat atio ion n sur surve veys ys are are acc accur urat atee and and freq freque uenc ncy y is is app appro ropr pria iate te..
I - IV
7.
Food Food and and oth other er cons consum umab able le item itemss are are not not pre prese sent nt in the the rad radio iois isot otop opee and and ch use/storage areas.
I -V
8.
Radi Radioi oiso soto tope pe work work and and st storag oragee are areas as and and equ equiipmen pmentt are are label abeled ed adeq adequa uate telly.
I - IV
9.
Radi Radioi oiso soto tope pe sour source ces/ s/sstock tock solu soluttions ions are are lab label eled ed adeq adequa uate tely ly..
I - III III
10. Radi Radioa oact ctiv ivee wast wastee is man manif ifes este ted d on bot both h side sidess of the the tag tag,, seco second ndar ary y cont contai ainm nm liquids.
I-V
11. Shie Shield ldin ing g is adeq adequa uate te (mat (mater eria ial, l, thic thickn knes ess, s, posi positi tion onin ing) g)..
I-V
12. Dosi Dosime mete ters rs,, if if ass assig igne ned, d, and and app appro ropr pria iate te prot protec ecti tive ve equi equipm pmen entt are are used used duri duri radioisotope radioisotope handling.
I-V
13. Fume Fume hood hoodss are are used used prop proper erly ly (sas (sash h set setti ting ng,, unc unclu lutt tter ered ed,, rat rated ed for for rad radio isot ot iois Sign up to vote on this title
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Individuals who frequent areas where radioactive materials are present and radiation workers be trained by the principal investigator according to the functions performed. This training m evaluated during inspections, either by discussions with individuals present or by written rec if they are used. A checklist (See PI Training Checklist Appendix) has been developed which be used to assist with the clarity and uniformity of the principal investigator training records.
Registration is required in advance for introductory safety training classes; dates of avai training sessions may be obtained by calling the ORCBS and/or by checking the Training Ho 2-SAFE (432-7233) or the ORCBS Web Page, http://www.orcbs.msu.edu. Advance regist is not required for refresher training, since dates, times and locations are announced in adv and attendees register during the class.
Ionizing Radiation Theory
Ionizing radiation has the ability to remove electrons from atoms, creating ions; hence, the "ionizing radiation". The result of ionization is the production of negatively charged free elec and positively charged ionized atoms. There are four types of ionizing radiation radiation involved tha th be classified into two groups: 1) photons, such as gamma and x-rays, and 2) particles, su beta particles (positrons or electrons), alpha particles (similar to helium nuclei, 2 protons a neutrons), and neutrons (particles with zero charge, electrically neutral). Photon electromagnetic radiation having energy, but no mass or charge; whereas particles have typi both mass and charge as well as energy. Neutrons have mass and energy, but no charge, an typically produced by man with machines, such as cyclotrons. All types of ionizing radiatio radiatio remove electrons, but interact with matter in different ways.
Particles are more highly ionizing; excitation and ionization are the primary interaction with m and potential for ionization increases as mass and charge increase. The range in tissue (de which the radiation may penetrate) for particles decreases as mass and charge increase. Pho because they have no mass or charge, are less ionizing but more penetrating in matter.
Ionized atoms (free radicals), regardless of how they were formed, are much more a chemically than neutral atoms. These chemically active ions can form compounds that that int with the process of cell division and metabolism. Also, reactive ions can cause a casca chemical changes in the tissue. The degree of damage suffered suffered by an individual expos Sign up to vote on this chemical title ionizing radiation is a function of several factors: type of radiation involved, form o Useful Not useful radiation, intensity of the radiation flux (related to the amount of radiation and distance from source), energy, and duration of exposure.
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This is important for for many reasons. When deposited in the human body, the half life life o radioactive material material present in in the body affects the amount of the exposure. exposure. If the radioa material contaminates contaminates a workbench or equipment, and is not removable, the amount of time b the contaminated items may be used again is determined determined by the radioactive half-life. half-life. Radiois decay using half-life minimizes costs and concerns in radioactive waste management. The equation which is used to calculate radioactive decay is shown below. A = A0 e- λ t
Where:
A A0 e λ
t
= Current amount of radioactivity = Original amount of radioactivity = base natural log ≈ 2.718 = the decay constant = 0.693/t1/2 (where t1/2 = half-life) = the amount of time elapsed from A0 to A
It is important to be careful of the units used for the time. Days, hours and years must n mixed in the calculation. Radiation Units
Two types of units are used for radiation, units of activity activity and units of exposure (dose). activity quantify the amount of radiation emitted by a given radiation source. Units of exp quantify the amount of radiation absorbed or deposited in a specific material by a radiation sou
In the world today, two sets of units exist. They are the Special units (Curie, (Curie, Roentgen, Ra Rem) and the SI or International International Units (Becquerel, Gray and Sievert). In the United State Special units must be used as required by Federal law. Therefore, in our discussions the used will always be the Special units. SI units are defined and described in the appendix on
Units of Activity The unit of activity for radiation radiation is the Curie, abbreviated Ci. Most laboratory facilities use millicurie (mCi, 0.001 Ci) or microcurie (uCi, 0.000001 Ci) amounts of radioactive mate Sign upvity to vote this title since reliable data can only be obtained using low levels of acti activity for on a given isotope. The Useful Not usefules or photons disintegrations (particles (particl is an amount of radioactive material emitting 2.22 x 1012 minute (DPM). (The international, or SI, unit for radioactivity is the Becquerel, defined a disintegration per second.) Activity can be measured measured with an appropriate radiation radiation dete
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required by NRC law that all records relevant to NRC licensed activities mus the necessary conversion maintained in units of DPM or microcuries. To make the
microcurie unit, the following formula must be used in all records of surveys, waste materia radioactive solutions generated within the facility. CPM/Efficiency = DPM DPM/2.22 x 106 = uCi
Units of Exposure The Roentgen, abbreviated as "R", is the unit for measuring the quantity of x-ray or ga radiation by measuring the amount of ionization produced in air. One Roentgen is equal quantity of gamma or x-radiation that will produce ions carrying a charge of 2.58 x 10-4 coul per kilogram of air. An exposure to one Roentgen of radiation with total absorption will yield ergs of energy deposition per gram of air. air. If human tissue absorbs one Roentgen of radiatio radiatio ergs of energy will be deposited per gram of tissue. (The international units do not includ Roentgen, but simply use the amount of energy deposited in air as the descriptive term.)
The Roentgen is easy to measure with an ion chamber, an instrument that will measure the ion one sign) produced in air by the radiation. radiation. The ion chamber has a readout in Roentgen per h fractions thereof, and is an approximation of tissue tissue exposure. The ORCBS, Nat Superconducting Cyclotron Laboratory (NSCL) and other departments with the potenti external radiation exposures use ion chambers for measuring exposure potential. It is instrument for gamma radiation; however, it is not quantitatively accurate for alpha, beta or ne radiation.
The rad and the rem are the two main radiation units used when assessing radiation radiation exposure rad (radiation absorbed dose), is the unit of absorbed dose, and refers to the energy depositi any type of radiation in any type of material. (The international unit for absorbed dose is the it is defined as being equal to 100 rads.) One rad equals 100 ergs of energy deposition deposition per gr absorber.
The rem (radiation equivalent man) is the unit of human exposure and is a dose equivalent (The international or SI unit for human exposure is the Sievert, which is defined as equal to rem.) It takes into account the biological effectiveness of different types of radiation. The organ is important when assessing radiation exposures, and a modifying factor is used in rad Sign up to vote on this title protection to correct for the relative biological effectiveness (RBE or quality factor). Als chemical form of the radiation producing the dose is of critical in assessing int Usefulimportance Not useful doses, because different chemicals bind with different cell and/or organ receptor sites. Additionally, some types of radiation cause more damage to biological tissue than other
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classification is based on the chemical form of the radioactive material, which affect biochemical pathway and resultant target organ, therefore determining the retention time.
The dose rate is proportional to the radiation flux (number of particles or photons/sq centimeter/second) centimeter/second) and is expressed in rem/hour or mrem/hour. (Radiation dosimeter dosimeter readin reported in mrem units). The dose rate can be estimated by using an ion chamber whe radiation source is a gamma or x-ray emitter. The ion chamber is useful in estimating dose fo radiation, but special detectors for alpha or neutron radiation are required.
Biological Effects of Ionizing Radiation
Injury due to irradiation irradiation is caused mainly by ionization within within the tissues of the body. radiation interacts with a cell, ionizations and excitations are produced in either biolo macromolecules or in the medium in which the cellular organelles are suspended, predomin water. Based on the site of interaction, the radiation-cellular interactions may be termed as direct or indirect.
Direct action occurs when an ionizing particle interacts with and is absorbed by a macromolecule in cell (DNA, RNA, protein, enzymes, etc.). etc.). These macromolecules macromolecules become abnormal abnormal structures whic initiate the events that lead to biological changes.
Indirect action involves the absorption of ionizing radiation in the medium in which the molecules ar suspended. The molecule which most commonly mediates this action is water. Through a complex set reactions the ionized water molecules form free radicals that can cause damage to macromolecules.
The most important target for radiation radiation in the cell is DNA in the nucleus. Biological effects when DNA damage is not repaired or is improperly repaired. repaired. Extensive damage to DNA can to cell death. Large numbers of cells dying can lead to organ failure and death for the indiv Damaged or improperly repaired DNA may develop into lymphoma and cancers in somatic Two kinds of effects may result.
Acute, or nonstochastic, effects are health effects, the severity of which varies with the dose and fo which a threshold is believed to exist. Radiation-induced cataract formation is an example of nonstochastic effect (also known as a deterministic effect).
Sign up to vote on this title randomly forNot which the probability o Delayed, or stochastic , effects, are health effects that occur Useful and useful the effect occurring, rather than the severity, is assumed to be a linear function of the dose withou threshold. Genetic effects and cancer incidence are examples of stochastic effects.
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It is important, when considering the real versus the perceived risk of radiation exposures, aware of the acute effects of large radiation radiation exposures. Without this information, information, one h comparison to determine whether the radiation one is handling presents an actual risk, or doe Often, fears exist that because the radiation is present and is measurable, a serious risk is pre The fact that we cannot see, smell, hear or feel the radiation sometimes magnifies the fears. table below shows the effects of various types of high radiation exposures. Effects of Acute Radiation Exposures in Humans Ra d ia ti o n Ex p o su r e 10000 R; single dose, whole body
500 - 1200 R; single dose, whole body
250 - 500 R; single dose, whole body 50% death rate 50 - 350 R and and higher; higher; single single dose, dose, whole whole body
100 R; Single dose, whole body 400 - 500 R; local, low energy x-ray 600 - 900 R; local to the eye 500 - 600 600 R to skin; skin; local local sing single le dose, dose, 200 200 keV keV 1500 - 2000 R to skin; skin; local local single single dose, 200 keV keV 25 R; single dose, whole body 10 R; single dose, whole body
Effects Death oc occurs wi within ho hours fr from ap apparent ne neurolog cardiovascular breakdown (Cerebrovascular syndrome) Dea Death occu occurrs wit within hin day days and and is asso assocciate ated wit with b diarrhea and destruction of the intestinal mu (Gastrointestinal syndrome) Death occurs several weeks after exposure due to dama bone marrow (Hematopoietic syndrome) Can produc producee various various degre degrees es of nause nausea, a, vomiti vomiting, ng, di reddening of skin, loss of hair, blisters, depression of im system Mild radiation sickness, depressed white blood cell co Temporary hair loss Cataracts Thresh Threshold old erythe erythema ma in in 7 - 10 days days,, follo followed wed by grad gradual ual and dull tanning Erythema, Erythema, blisteri blistering, ng, residua residuall smooth smooth soft soft depresse depressed d scar Lymphocytes temporarily disappear from circulating b Elevated nu number of of ch chromosomal ab aberrations in in pe pe blood; no other detectable injury or symptoms
External and Internal Radiation Exposures
There are two potential primary exposure types connected with work involving radioisot external and internal exposure to radiation. Each must be carefully evaluated prior to working radioactive materials, and precautions must be taken to prevent these exposures. Sign up to vote on this title
External Radiation Exposure Useful Not useful External hazards arise when radiation from a source external to the body penetrates the bod causes a dose of ionizing ionizing radiation. These exposures can be from from gamma or x-rays, x-rays, neu alpha particles or beta particles; they are dependent upon both the type and energy of the radiat
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The onset of first observable effects of acute radiation exposure, diminished red blood cell c may occur at a dose of approximately approximately 100 rads of acute acute whole body radiation exposure. exposure. The for humans (lethal dose where 50% of the exposed population may die from a one time exp of the whole body) is about 500 rads, assuming no medical intervention.
Exposure to external radiation may be controlled by limiting the working time in the radiation working at a distance from the source of radiation, inserting shielding between the worker an source, and by using no more radioactive material than necessary.
Internal Radiation Exposure Radioactive materials may be internally deposited in the body when an uptake occurs throug of the three routes of entry: inhalation, ingestion and skin contact. These exposures can when radioactive material is airborne; is inhaled and absorbed by the lungs and deposited i body; is present in contaminated food, drink or other consumable items and is ingested; spilled or aerosolizes aerosolizes onto the skin and absorbed or enters through through cuts or scratches. deposition may also result from contaminated hands, with subsequent eating or rubbing of ey
Internal exposures arise when radiation is emitted from radioactive materials present withi body. Although external hazards are primarily caused by x-rays, gamma rays, high energy and neutrons, all forms of radiation (including low energy betas, gammas and alphas) can c internal radiation exposures. Alpha particles create a high concentration of ions along their and can cause severe damage to internal organs and tissues when they are inhaled, ingested present on the skin. skin. Once these particles get into the body, damage can occur since there protective dead skin layer to shield the organs and tissues. Internal exposures are not limited intake of large amounts at one time (acute exposure). exposure). Chronic exposure may arise arise fro accumulation of small amounts of radioactive materials over a long period of time.
It is known that many substances taken into the body will accumulate in certain body organs, c target organs. For example, iodine will accumulate in the thyroid gland. When iodine is inha ingested, the body cannot distinguish stable iodine from radioactive iodine; a significant porti the inhaled iodine will be deposited in the thyroid gland within 24 hours.
Other elements, such as calcium, strontium, radium and plutonium accumulate in the bones. high doses to bones can occur over very long periods of time, since the body eliminates materials very slowly slowly once they are incorporated incorporated into the bone structure. The blood for organs, such as the bone marrow, are very radiosensitive,Sign since marrow up tobone vote on this titlecells are in t phase of mitotic activity more often than other cells. Hence, if there Not is auseful significant long Useful exposure to radioisotopes, radioisotopes, chronic diseases such as leukemia leukemia and/or osteosarcoma can occur induction time for the onset of these types of diseases is typically in excess of 20 years.
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Michigan State University possesses a radioactive materials license which contains fu conditions of operation.
All of the above laws, guidelines and regulations must be obeyed. If any of the regulating age or authorities determine that the laws or conditions are not complied with during the per inspections which they conduct, violations will be cited, and penalties may be imposed. Pen may include civil penalties (which may be fines or criminal prosecution in court), sanct suspension or termination of the license. For this reason, reason, it is imperative that all prin investigators, workers and support staff involved in the receipt, use, disposal or recor radioactive materials be aware of and comply with these laws.
The Code of Federal Regulations, Title 10, Parts 19 and 20, are legal requirements set forth f radioactive materials licensees. In particular, Part 20 contains the general practices, requirem and conditions by which all users of radioactive materials must abide. On January 1, 199 revised Title 10 Code of Federal Regulations, Part 20 became law for all licensees. Num changes were made; most of these changes pertain to the way the programs and operation managed, and are the responsibility of the Health Physics staff. One change should be particu attended to by all Michigan State University staff. In the revised 10 CFR 20, ALARA pract prac mandatory. ALARA
ALARA is an acronym meaning As Low As Reasonably Reasonably A chievable. It is a requireme the law, meaning all facilities possessing radioactive materials licenses must have a formal AL program. It may be defined as a professional standard standard of excellence, and is practiced by ke all doses, releases, contamination contamination and other risks as low as reasonably achievable. The regu guideline and our license requires managing programs and procedures to achieve ≤ applicable legal limits, such as air and water release limits, exposure limits or contamination l for radiation use facilities.
Michigan State University has not needed to change its management practices significantly wit implementation of this new law, since ALARA was written into the license previously an been practiced here for many years. MSU has attempted to incur no exposures, exposures, releas contamination, but since this is not feasible or practical in radiation use facilities, they are beneath 10% of the legal limits. Sign up to vote on this title
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It is not a violation of the law to exceed an ALARA guideline; however, these occurrences radiation safety staff and radioactive materials users to situations which need to be review determine whether the practices may be modified to better reflect ALARA management prac
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The exposure limit for whole body exposures is lower than that for a single organ becaus organs and tissues are exposed in a whole body exposure, while only a single organ is involv the single organ exposure limits. limits. The risk to the organ is incorporated in the exposure exposure calcula which must be done if organs or tissues are exposed. Maximum permissible exposure lim external radiation for adult and minor radiation workers are given in the table below. OCCUPATIONAL RADIATION EXPOSURE LIMITS Part of Body
Adult Yearly (mrem)
Minors Yearly (< 18 yrs. age) (mrem)
Adult ALARA Yearly (mrem)
Whole Body, Head and Trunk, Active Blood Forming Organs (TEDE) Lens of Eye (LDE) Extremities (SDE) (Elbows, Forearms, Hands, Knees, Lower Legs, Feet) Single Organ Dose (TODE) Skin of Whole Body (SDE)
5,000
50 0
5 00
1 5 , 0 00 5 0 , 0 00
1,500 5,000
1,500 5,000
5 0 , 0 00 50,000
5,000 5,000
5,000 5,000
New dose quantities were incorporated incorporated in the 10 CFR 20 law which took effect effect on 1/1/94. that each of the following quantities quantities are types of dose equivalents. equivalents. The following defin describe the new quantities. quantities. (Note: the types of doses are are quantities; the units units used for quantities are the rem or the Sievert.)
DE: Dose Equivalent. The product of the absorbed dose in tissue, quality factor, and all othe necessary modifying modifying factors at the location of interest. The units of dose equivalent are the rem and sievert
CDE: Committed Dose Equivalent. Means the dose equivalent to organs or tissues of referenc that will be received from an intake of radioactive materials by an individual during the 50 year perio following the intake.
the orga EDE: Effective Dose Equivalent. It is the sum of the products of the dose equivalent to Sign up to vote on this title or tissue and the weighting factors applicable to each of the body organs or tissues that are irradiated.
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CEDE: Committed Effective Dose Equivalent. It is the sum of the products of the weightin factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalen to these organs or tissues.
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Personnel Monitoring
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Radiation detection dosimeters (badges) must be worn routinely by personnel when exposu penetrating radiation is possible. possible. At Michigan State University, this means that workers han radiation that is energetic enough to penetrate and cause exposures need to wear a dosim Dosimeters are exchanged exchange d quarterly, and in some locations, monthly. Each individu responsible for seeing that his/her badge has the current dosimeter within the holder.
These badges provide legal documentation of external radiation exposure received while wo with radioactive materials at a given facility. They are not to leave your immediate work area are not to be taken home or to any other location, since non-occupational exposures may (e.g., a dentist’s office or another laboratory). Badges are heat and light sensitive, and if lef car where the temperature may be high, a false exposure will be recorded. It will then be difficult to distinguish a true radiation dose from a dose caused by exposure to excessive he light.
Radiation detection dosimeters are not assigned for work with certain radionuclides, sinc energies are beneath the detection limit of the badge. This is not a risk risk to the worker, how because these kinds of radiation are not penetrating enough to cause a deep radiation Examples of these radionuclides are 3H, 14C, 35S, 45Ca, 33P and 63Ni.
For those individuals who use x-ray equipment and/or high energy beta or gamma emi extremity (ring) badges should be used in conjunction with the whole body dosimeter. legal requirement that workers handling ≥ 1 mCi of 3 2 P must wear extre badges. The whole body badge should be worn on the torso with the name tag facin suspected source of radiation. With finger ring ring badges, the name tag must must face the rad source.
Care should be taken to make sure that badges do not become contaminated with radioa materials. Lost or misplaced badges should be reported immediately to the ORCBS in receive a replacement. Under no circumstances should workers wear a dosimeter belongi another individual. individual. It is a legal requirement requirement that doses be tracked tracked for the worker to who dosimeter is assigned.
When terminating employment with the university, badges must be returned to the ORCB Sign up to vote on this title badges are not returned and proper notification of termination of employment/study ha occurred, it is a non compliance with regulatory regulatory requirements. report Not useful Useful A termination supplied when a worker leaves, since the next place of employment must be supplied with report before the individual will be allowed to work with radioactive materials.
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Minors Working With Radioactive Materials
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Radiation exposure limits exist for minors, (individuals under 18 years of age) who work radioactive materials. These limits are 10% of all of the occupational limits for adult rad workers. For these workers, workers, safety training training must be completed prior to to work with radioa materials as with other occupational occupatio nal workers. It is university policy that an informed par consent form must be completed and kept on file for purposes of liability and risk managemen
Due to university policy and legal requirements, principal investigators must notify the OR before allowing minors to handle radioactive materials. Pregnant Radiation Workers
A special situation arises when a radiation worker becomes pregnant. Under these condi radiation exposure could also involve exposure to the embryo or fetus. A number of studies indicated that the embryo or fetus is more sensitive than the adult, particularly during the firs months of pregnancy. This can be a problem since many workers are unaware of their pregn during the first month or two of gestation. gestation. Hence, the NRC and the State of Michigan requir all occupationally exposed workers be instructed concerning the potential health prote problems associated with prenatal radiation exposure.
The maximum permissible exposure for a declared pregnant worker during the gestation per 500 mrem. There are relatively few research laboratories where radiation levels are high en that a fetus would receive this dose before birth. birth. If a radiation worker is pregnant, pregnant, she may n the Radiation Safety Officer, and then declare the pregnancy in writing in order for the pre exposure limits to take take effect. The pregnant radiation worker will will then meet with a health ph staff member, and a complete assessment of her radiation exposure potential will be made. written declaration is made by completing a Declaration of Pregnancy form, which is maintain the records by the ORCBS. If notification is not made in writing, the radiation exposure limits remain at the occupational that is, 5 rem rem per year. An individual may "un-declare" her pregnancy at any time, but should be documented.
Declared pregnant workers (DPW) will be assigned two badges, one foronthe Sign up to vote thiswhole title body, nor worn on the torso and one for the fetus, fetus, normally worn on the abdomen. The badges w Useful Not useful exchanged on a monthly basis. basis. Exposures must must be maintained beneath a cap of 50 mrem month in order to prevent exposure spikes.
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Area Restrictions
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All rooms or areas in which licensed quantities qua ntities of radioactive materials are used or stored mu posted with a "Caution Radioactive Material" sign, an "NRC Licensing and Regulation Inform Bulletin" sign, sign, and a "Notice To Workers" Workers" sign. Door signs must must include the pri investigator's name and phone number, and where he or she can be reached in the event emergency. Postings can be obtained from from the ORCBS. The following chart definitions are set forth in the federal law for area restrictions. DEFINITION OF AREA RESTRICTIONS 10 CFR 20.1003 Unrestricted Area An area, access to which is neither controlled nor restricted by the licensee. Restricted Area An area, access to which is limited by the licensee for the purpose of protecting individuals against undue risks from exposure to radiation and radioactive materials. A restricted area does not include areas used as residential quarters, but separate rooms in a residential building may be used as a restricted area. Controlled Area An area, outside of a restricted area but inside of the site boundary, access to which can be limited by the licensee for any reason. Radiation Area An area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 5 mrem in 1 hour at 30 centimeters from the radiation source or from any surface that the radiation penetrates. High Radiation Area An area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 100 mrem in 1 hour at 30 centimeters from the radiation source or from any surface that the radiation penetrates. Very High Radiation Area An area, accessible to individuals, in which radiation levels could result in an individual receiving an up to vote on this title any surface absorbed dose in excess of 500 rads* in 1 hour at 1 meter from Sign a radiation source or from that the radiation penetrates. Useful Not useful
*The exposure rates for Very High Radiation Areas are in rads, rather than rems, because potentially life threatening exposures could result in areas with these fluxes of radiation.
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have been using the unrestricted area limits for several years at Michigan State University as of our ALARA program management.
Another very important requirement for restricted areas is the security of radioactive materials the responsibility of all workers frequenting a restricted area to maintain security. discussed in the section on security of radioactive materials.
Other radiation area restriction categories (radiation area, high radiation area, etc.) exist onl few specific locations, which are typically not accessible to the general public. In the emergency or other unusual situations, any of the restricted areas may be restricted to a secure level to protect against radiation or any other hazard which may be present. If this w occur, the area(s) would be clearly marked and posted with warning signs or barriers.
Warning signs and labels are available from the ORCBS. Indiscriminate Indiscrimina te use of warning and/or labeling of non-radioactive materials with "Radioactive" stickers or labels is prohibited. Labeling Requirements
Work areas, trays, racks, stock solutions, tools, equipment, etc., which contain radioa material or are are contaminated must be labeled labeled with radioactive radioactive materials tape. The label contain the radioisotope present, date, and the total activity in disintegrations per minute (DP microcuries. It is not reasonable to expect that each tube or vial be labeled, but the contai or rack that holds them must be labeled. labeled. (For example, scintillation scintillation vials do not need individually labeled, but the tray or box that they are stored in must have the above desc label). The "rule of thumb" is that if there is radiation radiation above the background in or on someth must be labeled.
For contaminated equipment which is in frequent use, the isotope, date and maximum ac which may be present at any given given time is to be written written on the radioactive radioactive warning label equipment which is used for radioactive materials, but is not contaminated (equipment whic staff wishes to identify for radioactive use), a label with the radioactive materials war "Caution, Radioactive Materials", may be used. Labels are not required if the equipment contaminated.
All radioactive waste must be similarly labeled with the the above information. Benc Sign updescribed to vote on this title waste containers are to be labeled in the same method as for radioactive materials Useful Not useful in use or sto As soon as radioactive waste is placed in the radioactive waste container, all information o waste tag must be filled out.
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Bioassays
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Conditions of the broad license issued by the Nuclear Regulatory Commission (NRC) man that bioassays are required for workers using certain types and amounts of radioisotopes.
Individuals performing or observing iodinations where one millicurie or more of 125I is use required to obtain a thyroid scan after the iodination or use of the sodium iodide or potas iodide stock solution. solution. A baseline thyroid thyroid scan should be conducted on workers who hav previously used these kinds of 125 I at Michigan Michigan State University. University. Individuals must must rece thyroid scan bioassay with the ORCBS at least 24 hours after each iodination or use of radioiodine, but not more than one week afterwards.
Also, individuals handling ≥100 mCi of tritium (3H) must submit a urine sample to the ORCB bioassay within 24 hours hours of the handling. This bioassay must must be performed each time this of tritium is handled. Contact the ORCBS for further details prior to urine bioassays.
If there appears to be a likelihood that a significant internal exposure has occurred, the Radi Safety Officer may require further bioassays as deemed necessary. Ordering Radioactive Materials
Any receipt of radioactive radioactiv e materials must be authorized by the ORCBS. Authorization Authorizatio n is bas prior approval by the Radiation Safety Committee as described described earlier. All requisitions shou sent to the purchasing department directly, who will contact the ORCBS to obtain authorizat order. The information that purchasing needs from from the approved user is the the name of the prin investigator ordering the material, account number, element and mass number, chemical f activity and company from which the radioisotope will be purchased. Every shipme radioactive material received must be inventoried.
Each shipment received by project leaders, such as gifts, electron capture devices, or any device containing a radioactive source or radioactive material must be reported to the ORCB that the material may be tracked in the inventory database and summed with the campus t This is to prevent an individual principal investigator or the campus from exceeding indiv approval or MSU license possession limits. Sign up to vote on this title
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Receiving and Monitoring Radioisotope Shipments
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It is required that we document any transfers of radioactive materials by reassigning the ship in our inventory database. To transfer a shipment, call the the ORCBS and supply the informat the Health Physics staff, who will confirm approval to transfer the material and documen change in the inventory database.
Radioactive materials must never be transferred to individuals who are not certified or appro Certified workers are trained and have passed the certification examination. Food and Drink Policy
Due to the number of NRC violations cited at numerous institutions, including MSU in violations, the MSU Radiation Safety Committee and the Office of the Vice-President for Res and Graduate Studies have developed a policy regarding food and drink. The following p must be adhered to by radioisotope principal investigators and users. Michigan State University Policy for Food and Drink in Laboratories
There shall be no food, drink, smoking or applying cosmetics in the laboratories which have licensabl radioactive radioactive materials, biohazardous materials materials or hazardous chemicals present. There shall be no storage, us or disposal of any "consumable" items in laboratories (including (including refrigerators within laboratories). laboratories). Room which are adjacent, but are separated by floor to ceiling walls, and do not have any chemical, radioactive o biohazardous agents present, may be used for food consumption or preparation at the discretion of th principal investigator investigator responsible for the areas.
It is important to be aware that even the presence of empty food and drink containers in the no trash may cause a violation, since it is construed as "evidence of consumption" by regulators the burden of proof to to the contrary then lies lies with the licensee. licensee. Please also note that that gum tobacco chewing are prohibited in laboratories.
Floor to ceiling enclosures must separate food areas from hazardous materials areas, due t potential for release of a hazardous material into the air, and then into a food area when only p barriers are present.
If empty food or drink containers are used for storage or disposal of laboratory waste, pipette or other laboratory equipment, reagents or materials, they must be clearly labeled. If use Sign up to vote on this title disposal of items contaminated with radioactive materials, the containers must be clearly la with the radioactive materials warning symbol, and the nuclide, quantity of activity useful and date. Useful Not Security of Radioactive Materials
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The personnel present in the laboratory may provide security for radioactive materia challenging unauthorized entry into the the room. Staff who are not radiation radiation workers may be a those in immediate control of the materials if they are trained by the principal investigator acco to the items on the PI Training Checklist. Inventory of Radioactive Materials
The NRC requires that all licensees maintain records tracking the receipt, use and dispos radioactive materials. materials. This is done with an inventory maintained maintained in a database at the OR Shipments of radioactive materials are logged into the database for each principal investi ordering the material. Additionally, workers using the material, training dates, locations material is used, monitoring equipment and radioisotope approvals are maintained in the data Periodically, a printout of information for a project leader will be sent to the laboratory information must be updated and corrections made. This information is a legal record subj inspection by any regulatory agency; efforts must be made to keep records as accurate complete as possible to prevent NRC violations.
Use logs are required in laboratories for nuclides with half-lives ≥ 120 days and for high nuclides. The log should contain records of amounts used, who used them and dates of u each shipment received. To determine what nuclides are high risk, refer to the Labor Classification Tables in the appendix. Shipment of Radioactive Materials
Shipments of radioactive materials leaving the university must have prior authorization o Radiation Safety Officers Officers at both the sending and the receiving institutions. institutions. Federal and Stat requires that the shipper must obtain the receiver's approval and the respective Nuclear Regu License number or the State License number prior to the shipment of the material.
All shipments must be in accordance with the packaging and labeling requirements set forth b Department of Transportation (DOT); an appropriate record must be made of the radiation leve contact with the package and at three feet from the package using an ion chamber. Also, the r must contain information on the shipper, receiver, nuclide(s) and activity, phone numbe shipper and receiver, and performance of a survey for removable removable Sign up toradioactivity. vote on this title Contact a H Physicist well in advance of the desired shipping date toUseful assure thatNotalluseful the required lic exchanges, shipping papers and monitoring records are completed, as the package will n shipped until these requirements are met.
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future locations, this information will be supplied to a worker leaving Michigan State Unive after the radiation detection badge has been returned to the ORCBS. Leak Tests of Sealed Sources
Each sealed source containing licensed material (other than tritium) with a half-life greater thirty days, and in any form other than gas, shall be periodically tested tested for leakage. The test be capable of detecting 0.005 uCi. Sources are exempt from testing if if they contain <10 uCi alpha emitting material or <100 uCi of a beta or gamma emitting radionuclide.
Sources that are being stored and not being used u sed must be tested at least once every ten years the exception of alpha emitting sources. sources. Alpha emitting sources sources must be tested every qu regardless of use.
A stored source is one that has not been used for six months, and will not be used in the co six months. It must be removed from its functional position (i.e., electron capture de removed from gas chromatographs) chromatographs) and secured. Stored sealed sources sources must be leak tested b being returned to service. The broad license requires that sealed beta or gamma emitting emitting sourc leak tested every six six months. Alpha emitting sealed sealed sources must must be leak tested ever months.
Principal investigators must have approvals to possess and use sealed radioactive sources. must have training, sources sources must be labeled, and security security must be in place. It is the prin investigator's responsibility to assure that the sources are used according to the laws regulations pertaining pertainin g to the source. In particular, the leak tests must be performed by the deadline. If non compliances are found with sealed sealed sources, sanctions may be imposed. Radiation Safety for Machine Produced Radiation
Radiation producing equipment such as diffractometers, x-ray spectrometers, electron acceler diagnostic and therapeutic x-ray machines, and electron microscopes are all regulated b Michigan Department of Public Health (MDPH), Radiological Health Division. Equipment o type must be registered with the the State of Michigan. A copy of this registration registration must be disp in the room with the radiation radiation producing equipment. Posted information shalltitle also include a Sign up to vote on shall this of Section 5 of the State of Michigan's Ionizing RadiationUseful Rules andNot form RH100 (Noti useful Employees). It is required that all work done with these machines will be in accordance wi rules set forth by the Michigan Department of Radiological Health Ionizing Radiation Rules.
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than 60 days, an alternate principal investigator with the appropriate radioisotope approvals be designated, and must agree to assume responsibility.
The ORCBS must be notified in writing of the absence duration and the nam the alternate principal investigator who will oversee the uses of radioa materials during the absence prior to departure. The stand-in PI must have al
authorizations necessary to oversee the uses of the radioactive materials possessed by the a PI. The ORCBS must be notified in in advance of the intended absence. During the abs shipments will still be logged under the absent principal investigator's inventory, but all over will be conducted by the stand-in PI.
Radiation Laboratories Laboratory Design and Equipment
Working with radioactive materials requires the use of specially designed laboratories equipment, and may not be conducted in offices or other unapproved locations. In fact, roo be used for such work must be examined and approved for the use of the types and quantit radioactive materials to be used. This is part of the approval process. Most laborat Michigan State University meet the requirements for use of radiation.
Smooth, contiguous, non-absorbent surfaces such as stainless steel or linoleum are preferred radiation work area. A properly working chemical fume hood with flow rates of at least 10 per minute is required if fume hoods will be used for containing radioactive materials. filters and/or design is not generally necessary, but may be prudent in special cases. The r used must be capable of security, or in other words must be able to be locked to maintai security requirements for radioactive materials.
In areas where contamination is likely, surfaces should be covered with absorbent and dispo material, such as poly-backed absorbent lab paper. (The paper should have the plastic side side d absorbent side up.) If you are in the process of designing a radioisotope lab, consult the H Physics staff for for information regarding regarding design and vendor catalogues. catalogues. Work areas shou localized to minimize the possibility of contamination spread, and also because surveys mu Sign up to vote on this title conducted for all areas where radioactive materials are used, stored or disposed.
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Equipment such as glassware, tools, syringes, etc. used in the handling of radioactive mat should not be used for other work or allowed to leave the lab unless it can be shown tha
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1 . Maintain Maintain neat and clean clean work work areas. areas. Clutter, Clutter, debris debris and crowded conditions conditions interfere interfere the careful handling required in hazardous materials use.
2 . Follow Follow experiment experimental al procedur procedures es carefull carefully. y. Radioisotop Radioisotopee approvals approvals are continge continge following the procedures, statements and representations made in the principal investig approval. Departures from the procedures may place the approval in jeopardy.
3 . Use absorbent absorbent poly-backed poly-backed laboratory laboratory paper, paper, with with the plastic plastic side down, down, to protect protect sur from inadvertent spills or splashes. Laboratory benches, fume hoods, trays conta samples, waste areas and floors in the radioactive work areas are some of the locations w absorbent paper is useful.
4 . Use secondary secondary containment containment for for all radioacti radioactive ve solutions, solutions, samples, samples, liquid liquid waste waste or any hazardous materials which may be spilled. Use trays, boxes, bus trays and other typ secondary containment to catch spills, splashes and possible container ruptures.
5 . When transporting transporting radioactive radioactive materials, materials, use use a cart; this will will prevent prevent accidentally accidentally dropp tipping the container. 6. Clean up the the work work areas areas and and survey survey for contaminati contamination on after after work is finish finish contamination is present, decontaminate or dispose of the contaminated materials.
7 . Use tightly tightly sealed sealed or capped containers containers when moving, moving, heating, heating, centrifuging centrifuging or vort Spills, evaporation, gases, container breakage or splashes may occur in any procedure w energy is put into the system. 8 . Label all all radioactive radioactive materi materials als and areas areas where radioact radioactive ive material materialss are used, st disposed. Unattended Operations
An experiment is considered to be unattended if there is no one present who is knowledgeab the operation and of the shutdown procedure to be followed in the event of an emergency.
devices t • Experiments that are left unattended must must have overriding controls automatic Sign upwith to vote on thisshutdown title prevent system failure that could result in fire or explosion, for example, the loss of cooling water Useful Not overheating, flooding, and pressure buildup. Permanent piping, and shields or useful barriers if necessary should be provided.
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• If your equipment is is potentially dangerous and must be left on overnight, consult with your supervisor see whether it is permissible to do so. Ensure that persons who may have to check the room can re-ent exterior doors (check with campus police). Notify the facilities manager (as some repair work an janitorial services are often performed during the night hours).
• Post a notice on your equipment describing describing possible malfunctions, malfunctions, emergency emergency shutoff procedures, procedures, and th nature of the hazards.
• Bunsen and other gas burners without approved flame-failure flame-failure devices must not be left on overnight. pressure often fluctuates; an increase in pressure will cause a taller, hotter flame, overheating equipmen and perhaps causing a fire. If the pressure decreases decreases the flame flame may go out. Upon resumption of gas flo unburned gas will accumulate to create a fire or explosion hazard. • Over-temperat Over-temperature ure cutoff devices devices should should be used on heated oil oil baths.
• Use permanent permanent piping piping if you must supply supply water to to an overnight overnight experiment. experiment. A sudden rise rise in pressu due to water fluctuations may rupture plastic or rubber experimental apparatus and cause flooding of lowe floors. Floor flooding also takes place when water is left running into sinks to maintain a desired and the drain becomes blocked or plugged. plugged. Consideration should should be given to the use of standing overflo devices, which make drain plugging less likely.
• Electrical Electrical extension extension cords shall never be left plugged plugged in while unattended unattended (they are for temporary temporary us while working with portable equipment in rooms where receptacles are not available). • Protect the cords of electrical devices that that must operate operate unattended. unattended. Prevent chemical chemical or physical dam to the cords, by draping cords away from foreseeable hazards and heat sources.
Monitoring Instruments
Every laboratory using radioactive materials must possess or have available for immediat appropriate radiation monitoring monitoring equipment. This equipment must be in good working orde must be calibrated yearly by the ORCBS Health Physics staff. staff. Results of this calibration w forwarded to the project leader. Equipment that has not passed this annual examination mu removed from service until it is repaired or replaced. If you believe that there is a problem your equipment, contact the ORCBS and arrange a time when the equipment can be inspecte calibrated. Sign up to vote on this title
Radioactive monitoring instruments must be capable of detecting the radioisotope being moni useful To calcula Not at or below the contamination limits listed in the section onUseful Radiation Surveys. sensitivity of the survey instrument, the following formula may be used.
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the detector. Radioisotopes which may be detected reliably with the beta pancake are 14 33P, 32P, 45Ca, 36Cl, and other beta emitting nuclides.
The low energy gamma (LEG) probe is used with the Geiger counter to detect and measure ga radioisotopes of various energies. It is most efficient for 125 I, but will perform adequatel 51Cr, 111In, 60Co and other gamma emitting nuclides. These detectors will also also detect low e x-rays, such as those emitted by beta emitters producing Bremsstrahlung radiation.
Another instrument in common use is the liquid scintillation counter. It is necessary to radiation safety surveys for 3H and 63 Ni, since no other instrument will detect these nucl Liquid scintillation counters work for both beta and gamma nuclides for quantifying what i sample. It is not an adequate primary method of evaluating contamination contamina tion surveys, however, samples measured consist of wipes of the areas of suspected contamination. If the contamin is not removable, the wipe will not pick it up, and contamination will not be detected . It possible for only part of the contamination present to come up on a wipe, not giving an acc measurement of the contamination present.
A third instrument which may be used to evaluate contamination is the gamma well cou Again, this is used to gather data in samples, but for the same reasons as the liquid scintill counter, it is not a good radiation survey instrument. instrument.
Ion chambers are used commonly by the Radiation Safety staff and in locations where frequen higher flux external radiation hazards are present; they are typically not used for contamin surveys by laboratory staff. These instruments measure the ions produced in air (of one sig gamma radiation, and are a good indicator of radiation radiation exposure fields. They are usef exposure potential screening on shipments, hot parts at the Cyclotron, drums of waste a Radioactive Waste Building, packages prior to shipment and sources and stocks of radioa materials.
Other more sophisticated instruments used to detect and quantify radiation are the ga spectrometer or multi-channel analyzer, neutron detectors, alpha detectors, and a wide arr electronic dosimeters, area monitors, and even portal monitors (which a person walks throu detect any contamination on the body or clothing; these are used at reactors). For effective and accurate data gathering in radiation, follow a few Sign up tosimple vote onguidelines: this title
Not useful Useful 1. Survey at the proper geometry. geometry. Hold the detector detector about 1 cm. or 1/2 inch inch abov surfaces monitored. If the detector is is too far away, serious underestimation of activ no detection of activity present may occur. If the detector is too close, contamination
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Calibrations
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Radiation detection instruments used for contamination surveys must be operable and capab detecting the radioisotopes used in the laboratory. To assure this, radiation detection instrum will be calibrated calibrated annually by the ORCBS. Calibrations are conducted using a set of s radiation check sources containing known amounts of activity. The percentage of the k activity that the instrument detects is known as the efficiency of the instrument. The source sourc for a range of radiation energies; instruments calibrated then can be evaluated as to performance and accuracy through the calibration.
After calibrating the instrument, a report of the results will be sent to the principal investig who should then place the report in the radiation safety record book maintained in the labora Instrument background, efficiencies for various appropriate nuclides used in the laboratory comments are on the record. This information information is to be used by laboratory staff when surveyi radioactive contamination in the work area. Instruments will be calibrated upon request, and must be recalibrated after repair. Radiation Surveys
The ORCBS will make independent surveys of all active Class B radioisotope labs at quarterly, and all Class C laboratories at least biannually. Such things as inventory assess contamination control, personnel monitoring, training and waste disposal practices w addressed during these these surveys. (See the survey checklist checklist used by the ORCBS in the Append
Copies of the results of surveys will be forwarded to the principal investigator, and a recheck be conducted in the event problems problems have been detected that need corrective action. action. The Radiation Safety Committee may accompany the ORCBS on surveys as deemed necessar problem laboratories or for purposes of auditing the radiation safety program.
Surveys are to be conducted by the project investigator or his/her designee in conjunction wi ORCBS surveys. Each lab that is actively using isotopes must conduct radiation surveys we monthly or quarterly, depending on the types and quantities of radioactive materials present laboratory. By doing this, the potential for exposures can be evaluated and reduced, if nece Records of these surveys must be maintained for review. Sign up to vote on this title
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When removable radioactivity is found, the area must be decontaminated and then re-surveye documented. Detectable levels of removable removable contamination should be removed, and removable contamination should be labeled and shielded whenever possible in order to mai
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RADIOACTIVE CONTAMINATION LIMITS AT MICHIGAN STATE UNIVERSITY
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T yp e of A re a
Alp h a E mitte r s (DPM/100
cm 2 )
High Risk Beta or Gamma Emitters (DPM/100 cm 2 )
Low/Moderate Risk Beta or Gamma Emitters (DPM/100 cm 2
Unrestricted Areas
22
220
2,200
Controlled Areas
22
220
2,200
Restricted Areas
2 20
2,200
22,000
Personal Clothing
22
22 0
2,200
22
22 0
2,200
Outside Restricted Areas Skin
Most of the radioisotope use areas on campus are treated as restricted areas, and are characte as locations with controlled access and have proper radiation safety controls in p Contamination limits for surveys are the controlled and unrestricted area li due to the ALARA programs required of licensees.
Radioisotopes classified as high risk include 45 Ca, 22 Na, and 60 Co. Low/moderate radioisotopes include 32 P, 3H, 14 C, 35 S, 125 I, 51 Cr and 111 In. Remember that the AL requirement must be adhered to in the above limits, meaning 10% of the li where possible. (For some radionuclides, it is impossible to achieve less than contamination limits, since the instrumentation and normal backgrounds prevent any incr sensitivity. sensitivity. For others, sensitivity sensitivity may may exist where it is realistic realistic to achieve achieve 10% o contamination limits.)
Practical Radiation Protection Sign up to vote on this title
Routes of Exposure to Radiation
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Minimizing the amounts of radioactive materials handled in all cases will reduce exposure pote
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Monitoring Operations Involving Radioactive Materials
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Due to the potential for contamination of work areas during use of radioactive materials necessary to monitor as much as possible the operations performed. Work areas shou checked before use to determine background or prior contamination. The survey instru instru should be turned on and placed proximal to the work area in order to check radiation levels, a alarm the worker if radiation levels rise significantly. Hands should be checked frequent presence of contamination due to splashing or aerosols. aerosols. At the end of the use of the work ar each day, work areas areas should be monitored to determine determine the presence of contamination. contamination. Not worker clothing and shoes shoes should also be monitored. If contamination is found, the ar equipment must be decontaminated. Time, Distance and Shielding
Three primary means of eliminating or reducing radiation exposures exist. They are:
Time: Minimize the time that radioactive materials are handled. Since the amount of exposure o as a function of duration of exposure, exposure, less time means means less exposure. This may be achiev conducting "dry runs" (practicing the procedures to be performed, with all of the step manipulations manipulation s performed without the hazardous hazardou s materials). Conduct the work quickl efficiently, but do not rush.
Distance: Maximize the distance from the the radioactive materials. Dose is inversely proportion distance, therefore, greater greater distance means less dose. dose. Do not increase the distance to to the wherein dexterity or control of the materials is jeopardized.
Shielding: Use shielding wherever it is necessary to reduce or eliminate exposure. By placin appropriate shield between the radioactive source and the worker, radiation is attenuate exposure may be completely eliminated or reduced to to an acceptable level. The type and am of shielding needed to achieve a safe working level varies with the type and quanti radioactive material material used. The HVL (half-value layer) layer) may be used as a guide to the thic of the shielding necessary to block the radiation. The HVL theonthickness Sign up toisvote this title of the shie necessary to reduce the radiation dose rate to half of the original unshielded Useful or Not useful dose rate. to the HVL information in the appendices on specific nuclides.
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Individuals using radioactive materials must wear laboratory coats, gloves and eye protec Additional protective equipment may be necessary or prudent. Contact a Health Physicist have questions about protective equipment. Airborne Radioactive Materials
Radioactive materials have the potential for release into the air, causing the worker to hav uptake of the material through one or more of the routes of entry into the body, particu inhalation. Numerous situations may cause airborne release of radioactive materials.
Contamination present in a room may create airborne radioactivity by simple movement o
air over the contamination, contamination, spreading it around in the air. air. Most radioisotopes radioisotopes will be picked air and spread through through this mechanism. This is one more more good reason to keep areas fr contamination.
Use of volatile forms of radionuclides, such as 1 2 5 I for iodinations or 3 H - s o d borohydride may generate airborne radioactivity. Any chemical or physical form which re volatilizes or evaporates into the air must be considered a potential airborne radioactivity risk.
contaminants. An exa Chemical reactions may generate radioactive gases or other airborne contaminants.
is the labeling reaction for 35S methionine, which generates a methyl mercaptan reaction w liberates HCl and 35SO2 gas. Airborne radioactivity has resulted in unnecessary intakes intakes and contamination in laboratories where the users were unaware of this risk and have not precautions to trap or contain the liberated 35SO2.
Heating or incubating may cause evaporation or chemical reactions which release radioa materials into the air. Aerosols (tiny droplets or particles) are present with all a ll materials, and
an increased risk when handling stock solutions or other high concentrations of radionuc Use chemical fume hoods or biological safety cabinets for high activity, concentrated or poten volatile radioactive materials manipulations.
Materials which have been frozen may release substantial quantities of aerosols or gas
radioactive material when the containers are opened. There have been numerous incidents at and other institutions where this has occurred and has caused significant contamination of Sign up to vote on this title areas, equipment and clothing of the worker opening the containers.
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Another cause of airborne radioactivity is media or solutions containing cells, bacteria or o living organisms. The living organisms metabolize the radioactive substrates and may pro
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In certain rare cases, respiratory protection may be necessary for certain radioisotope However, respiratory protection should only be used when other means of control and contain do not provide enough protection. Respirators must be chosen carefully to ensure the prop and type of cartridge, and the use must be monitored monitored carefully. For this reason, use of respi respi for radioactive materials use must be pre-approved by the ORCBS, documented and monit Prior to using respirators for any reason, fit testing and medical monitoring are required.
If you are concerned that an intake has occurred, contact the ORCBS. Bioassays (urine sam or other investigational methods may be employed to determine whether an intake has act occurred and to recommend ways to avoid such undesirable situations in the future.
Disposal of Radioactive Waste
The ORCBS has developed a manual entitled Michigan State University Waste Disposal G This manual describes the requirements and specific procedures for correctly managing disposing of hazardous waste, including radioactive, chemical, biological and pathological w Please use this guide when preparing waste for disposal. disposal. All radioactive waste shall be sepa from non-radioactive waste. Under no circumstances is it permissible to dispos any radioactive material into the non-radioactive trash or into any drains.
The issue of radioactive waste disposal is very complex, due not only to the radioactive natu the waste and its inherent disposal problems, but also the recent concerns with the chem hazards associated associated with the same waste. Hence, it is possible to have mixed waste, which which co not only radioactive waste, but RCRA (Resource Conservation and Recovery Act) haza chemical waste. Liquid scintillation vials are an example, because the toluene is hazardous the RCRA laws, due to flammability. Resultantly, radioactive waste must be properly manif for the isotope and activity, and any other hazardous constituents, including chemic biohazardous components. compo nents. Complete waste disposal instructions may be found in the Mic State University Waste Disposal Guide.
Radioactive waste must be completely labeled at all times, from the time it is deposited i container until final disposal. Records of radioactive waste disposal must be maintained b university for NRC review, so this labeling or “manifesting” is critical. Tags must be comp filled out at all times after any radioactive waste is placed in in the container. (Note: The rad to voteaccording on this titleto NRC law. warning label and certain other information on the tag mustSign be up present
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The ORCBS supplies the solid and liquid waste containers to laboratories upon request. responsibility of the laboratory to supply secondary containers, such as a plastic bus tra
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radioactive waste containers. This can be achieved by carefully monitoring potential radioa waste with an appropriate survey meter prior to disposal.
Since radioactive waste must be stored for some period of time prior to disposal, it is critica the date(s) the waste was deposited in the container be present; radioactive decay is one mea effectively managing and minimizing radioactive waste.
Due to the problems in radioactive waste management and legal requirements, no radioactive w may be removed from the laboratory laboratory without the complete information information on the tag. Chronic f to thoroughly manifest radioactive waste may result in suspension of permission to use radioa materials. Quantifying Levels of Radioactivity in Waste
Radioactive and other hazardous materials must be completely manifested in the waste. In or accurately list levels of radioactivity on the tags, it is necessary to assess the levels whic disposed in both liquid liquid and solid waste. Suggestions on methods to to quantify the waste foll
1 . During During a given experi experiment ment it it is known known that a certai certain n quantity quantity of radionuc radionuclide lide is is used. end of each of several similar experiments, take a sample of liquid waste and count it wi appropriate counting equipment. The activity in the sample per unit volume is then mult by the total volume of the liquid waste generated. generated. For the solid waste, the quant radioactivity in the liquid is subtracted from the total quantity used in the experiment, an remainder is then the quantity in the solid waste. Example: Total Used in experiment: Liquid Sample Volume: Total Liquid Waste Volume: Activity in Liquid Waste Sample::
500 uCi 1 ml 4000 ml 8 E-2 uCi/ml
Liquid Waste Total Activity: Solid Waste Total Activity:
8 E -2 uCi/ml X 4000 ml. = 320 uCi in liquid waste 500 uCi - 320 uCi = 180 uCi in solid waste Sign up to vote on this title
2 . After After the first first few experiment experiments, s, or when the waste waste carboy carboy is full, take take a sample of the p Not useful Usefulof the sample liquid waste, and count it as above. Multiply the activity per unit volum the total volume in the carboy to obtain the total activity in the carboy. Quantify the waste as above by subtracting the liquid waste activity.
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5.
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Store and transport transport radioactiv radioactivee materi materials als in contai containers ners which will prevent prevent breaka breaka spillage. Secondary containment is important; when transporting transporting radioactive material trays and carts. 6 . Use vent ventila ilatio tion n hoods hoods or glove glove boxes boxes if if the radio radioact activi ivity ty may may become become airbo airborne rne and and fo activity uses, such as stock solutions. 7 . The indivi individual dual(s) (s) respons responsibl iblee for any any contam contaminat ination ion will will be requi required red to to decontam decontamina ina area of concern. 8 . Regular Regularly ly check check your your hands, hands, cloth clothing ing and and shoes shoes for for contam contamina inatio tion n prior prior to leavi leaving ng th area after working with radioactive material. 9 . Always Always dispos disposee of radioact radioactive ive waste waste in a radioac radioactiv tivee waste waste containe container. r. 10. Always Always wear your your assigned assigned radiati radiation on detection detection badge(s badge(s)) when working working with with radi materials. 11. Wear laboratory laboratory coats when working working with with radioactive radioactive materials. materials. Lab coats shou buttoned up, not worn open. 12. Users Users of high high energy energy beta or gamma gamma nuclid nuclides es should should wear wear eye protect protection, ion, such such as s glasses or eye glasses.
Radiation Incidents/Emergencies The following are the reporting information necessary to evaluate and respond properly abnormal occurrence involving radioactive materials. • • • • • • • • • • • •
Radi Radion onuc ucli lide de invol nvolve ved d Amou Amount nt of radi radioa oact ctiv ivit ity y Chemical Chemical form form of rele release ased d materia material, l, other other hazard hazardous ous chemi chemical calss involve involved d Volu Volume me or rele releas ased ed mate materi rial al Locat Locatio ion n of inci incide dent nt (bui (build ldin ing g and room room num number ber)) Persons Persons conta contamin minated ated or expose exposed, d, estim estimate ate of of amount amount (e.g. (e.g.,, 2,000 2,000 CPM, CPM, 32P, 10 on skin of arm) Any Any inju injuri ries es,, what what the they y are, are, how how ser serio ious us Air Air bor borne ne radi radioac oacti tivi vity ty pres presen entt or or not not What Wh at you you have have done done so far Prin Princi cipa pall inv inves esti tiga gato torr nam namee Name Name of pers person on repo report rtin ing g Sign up to vote on this title Teleph Telephone one numb number er wher wheree you you can can be be rea reache ched d
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Some radiological incidents involve involve serious risk to to life, health or property. In the event of se injury coupled with exposure to radiation, fire, explosion, major release of health threate
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A minor incident with radioactive materials is an abnormal occurrence invo low amounts of radioactive materials, where the worker handling the spill k how to clean it up, has the decontamination materials on hand, and can res without incurring risk of exposures or spreading within a reasonably short tim
A major incident is an abnormal occurrence involving high amounts of radioa materials, high risk nuclides, large areas contaminated, contamination of the airborne radioactivity, or any situation where contamination may have spread outside the authorized area. Major spills must be reported to the Radi Safety Officer or his/her designee immediately, as required by federal law. the ORCBS during working hours; dial 911 during non working hours.
An e m e r g e n c y is an incident which involves serious injury or death, explosion, or significant release of a health or life threatening material, whic or may be coupled with a minor or major radiological incident. DIAL IMMEDIATELY IF AN EMERGENCY HAS OCCURRED!!
In the event of a MINOR incident, these procedures should be followed: 1. 2. 3. 4.
5. 6. 7. 8. 9.
Notify Notify the the princi principal pal inves investig tigator ator and perso persons ns in the the area area that that an incid incident ent has has occurr occurr Contai Contain n the the spil spill. l. Cover Cover with with absor absorben bentt paper paper or dike dike with with abs absorb orbent ent.. Isola Isolate te the the area area to preve prevent nt unnec unnecess essary ary spre spread ad and and perso personne nnell exposu exposures res.. Survey Survey usin using g the appr appropr opriat iatee monito monitorin ring g equipmen equipmentt in order order to to evaluat evaluatee the pres pres contamination on an individual's individual's skin and clothing and on lab equipment. equipment. If sk clothing contamination is present, a major spill has occurred. Contact the OR immediately. Using Using dispo disposab sable le glove gloves, s, caref carefull ully y fold fold up the abso absorbe rbent nt paper paper and and pad and and depo appropriate radioactive waste container. Surv Survey ey the the are areaa of the the spi spill ll to deter determi mine ne the the ext extent ent.. Deconta Decontamin minate ate the the spill spill using using decont decontami aminant nant dete deterge rgent nt (avail (availabl ablee from Gener General al St and resurvey. Contin Continue ue step step 7 unti untill the the area area is is decon decontam tamina inated ted comple completel tely. y. Docu Docume ment nt spi spill ll in rad radia iati tion on sur surve vey y log log book book..
In the event of a MAJOR incident, the following procedure should be instituted: 1. 2.
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Notify Notify all all perso persons ns in in the the area area that that a major major spill spill orUseful incide incident nt has hNot as useful occur occurred red and and ev unnecessary personnel. Notify the principal investigator. If possi possible, ble, preve prevent nt the the spreadi spreading ng of the the radioa radioacti ctive ve materi material al by usin using g absorbe absorbent nt p Do not attempt to clean it up. Confine all potentially contaminated individuals in or
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In the event of an EMERGENCY in which radioactive materials are involved, the follo procedure should be instituted: 1. 2. 3.
Notify Notify all pers persons ons in the the area area that that an EMER EMERGEN GENCY CY has has occurr occurred ed and and evacuat evacuatee the a risk to persons present exists. ex ists. Dial Dial 911 and and NOTIF NOTIFY Y of the the nature nature emer emergenc gency, y, using using the the repor reporting ting guideli guidelines nes previ previ listed in this section. AWAIT AWAIT THE THE EMERG EMERGENC ENCY Y RESPON RESPONDER DERS S who who will will assist assist and provide provide directi directi well as contact any other necessary responders.
All incidents involving radioactive materials must be reported as soon as pos to the principal investigator. If the principal investigator is not available, n the ORCBS, who will advise and assist with the problem. Decontaminating Radioactive Material
When radioactive material is in an unwanted or unplanned location, it is called contamination. may be floors, equipment, work areas, storage areas, people or areas outside the autho radiation use laboratory. Fortunately, Fortunately , most radioactive contamination and/or spills are clean to background levels levels in a reasonable reasonable time and with with reasonable cost. cost. Some metho decontamination are as follows:
Concentrated liquid decontaminating agent available from General Stores and most scientific suppliers. suppliers. This detergent is diluted with and rapidly and easily cleans radioactive contamination without without excessive effort. Mild wip scrubbing will remove most contamination using this detergent. Note that these detergents co a carcinogen, so the Material Safety Data Sheet should be read by new radiation users so tha are aware of the hazards. In dilute liquid form, form, radioactive decontaminants do not pres significant hazard to handlers unless ingested or splashed in eyes. Avoid prolonged skin co with the concentrated material. Liquid Radioactive Decontaminant:
Foam Spray Decontaminant: A variety of foam spray decontamination products are ava
which are marketed as radioactive radioactive decontaminants. decontaminants. However, many other foam cleaning pro accomplish decontamination just as effectively at a much lower cost; most of these are market any store as bathroom or kitchen cleaning agents. Spray the foam the areas, Sign up toon vote oncontaminated this title for a few minutes, then wipe off with a dry paper towel. Useful Not useful
Other Decontaminating Agents: Many other agents will work to clean radioa contamination that has been resistant to the above methods. Contact a Health Physici
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PI Number_____
(For ORCBS use
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APPLICATION FOR APPROVAL TO OBTAIN AND USE RADIOACTIVE MATERIALS AT MICHIGAN STATE UNIVERSI Please complete the requested information and send to: Radiation Safety Officer Office of Radiation, Chemical and Biological Safety C124 Research Complex - Engineering Campus Please call 355-0153 if you have questions.
1.
Name of of Princip Principal al Invest Investigato igator:__ r:________ ___________ __________ ___________ ____________ ___________ __________ __________ _____
Title:_______________________ Title:___________________________ ____ Department:_______________ Department:_____________________________ ______________
Office Location:_______________________ Location:_____________________________ ______ Telephone:___________________ Telephone:___________________
Date of Application:_____________ Application:_________________________ ____________ Fax Number:__________________ Number:__________________ 2.
Radiois Radioisotop otope(s e(s)) reque requeste sted d in in this this applica applicatio tion: n:
Nuclide
Physical and Chemical Form
Maximum Posse Amount (mCi)
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Radioiso Radioisotopes topes for which which previ previous ous approval approval was granted: granted: Location of previous approval:_________________________________________ approval:_________________________________________
Nuclide
4.
Physical and Chemical Form
Maximum Amou (mCi)
Describe Describe your formal formal experience experience handling handling radioacti radioactive ve material materials, s, includi including ng locations locations,, radioisotopes radioisotopes and amounts handled.
__________________________________________________________________________
__________________________________________________________________________
__________________________________________________________________________
__________________________________________________________________________
__________________________________________________________________________ List the safety training courses you have attended. Name of Course
Location (Institution) Sign up to vote on this title
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Mo./Yr.
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6 . Describe Describe the personnel personnel (dosimeters (dosimeters)) monitoring, monitoring, laboratory laboratory monitori monitoring ng (survey (survey and any o
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and protective equipment that will be used for each nuclide.
Dosimeters:_____________________________________________________________ Monitoring Equipment:
Make_____________________Model_ Make_____________________Model____________Detec ___________Detector____________ tor______________________ __________
Make_____________________Model_ Make_____________________Model____________Detec ___________Detector____________ tor______________________ __________ Protective Equipment: Lab Coats
t
Eye Protection
t
Gloves
t
Fume Hood
t
Shield
t
Type of Shield_______________________Thickness Shield_______________________Thickness:______ :______
Other (Describe): _________________________________________________________ 7 . Describe Describe the experimen experimental tal procedures procedures that that will will be utilized utilized with the the requested requested isotope. isotope.
Emphasize aspects that pertain to safety issues. A brief description of materials and meth is usually adequate. adequate. (Add more pages if necessary.) necessary.)
__________________________________________________________________________
__________________________________________________________________________
__________________________________________________________________________
__________________________________________________________________________
__________________________________________________________________________
__________________________________________________________________________
__________________________________________________________________________
__________________________________________________________________________ Sign up to vote on this title
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•What amount of radioactivity will be used in a typical experiment? __________________
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•What is the frequency of experiments?________________________________________ experiments?________________________________________ 8 . Describe Describe the types types of waste waste that will will be generated generated in this this research, research, including including physical physical and
chemical forms. List any other hazardous constituents, such as hazardous chemical, biolo hazards, etc. Identify the amounts, volumes and rates of disposal disposal of the waste.
__________________________________________________________________________
__________________________________________________________________________
__________________________________________________________________________
__________________________________________________________________________
__________________________________________________________________________
__________________________________________________________________________
__________________________________________________________________________
__________________________________________________________________________
9 . Please describe describe any any special hazards hazards associat associated ed with the use(s) use(s) of radioact radioactive ive materials materials req in this application.
__________________________________________________________________________
__________________________________________________________________________
__________________________________________________________________________
__________________________________________________________________________
__________________________________________________________________________
__________________________________________________________________________ Sign up to vote on this title
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CARBON - 14
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[14 C ]
PHYSICAL DATA
•
Beta Energy:
• • • •
Physical Half-Life: Biological Half-Life: Effective Half-Life: Effective Half-Life:
156 keV (maximum) 49 keV (average) (100% abundance) 5730 years 12 days 12 days (bound) 40 days (unbound)
•
Specific Activity:
4460 mCi/gram
• • •
Maximum Beta Range in Air: Maxi Maximu mum m Bet Betaa Ran Range ge in Wate Water/ r/Ti Tiss ssue ue:: Maximum Ra Range in in Pl Plexiglas/Lucite/Plastic:
24.00 cm = 10 inches *0.28 mm = 0.012 inches 0.25 mm mm = 0.010 in inches
*Fraction of 14 C beta particles transmitted through dead layer of skin: At 0.007 cm depth = 1%
RADIOLOGICAL DATA
• • • •
Critical Organ: Fat Tissue Routes of of In Intake: Inge ngestion, In Inhalation, Sk Skin Co Contact External exposure: Deep dose from weak 14C beta particles is not a radiological concern Inte Intern rnal al expo exposu sure re & cont contam amin inat atio ion: n: Prim Primar ary y radi radiol olog ogic ical al conc concer erns ns
•
Comm Commit itte ted d Dos Dosee Equ Equiv ival alen entt (CD (CDE) E):: (Fat Tissue)
•
Committe Committed d Effective Effective Dose Equivale Equivalent nt (CEDE): (CEDE): 1.54 mrem/uCi mrem/uCi (ingeste (ingested) d)
•
Ann Annual ual Limi Limitt on Int Intake ake (AL (ALI) I)*: *:
2.08 2.08 mrem mrem/u /uCi Ci (ing (inges este ted) d) 2.07 mrem/uCi (puncture) 2.09 mrem/uCi (inhalation)
2 mCi (ing (ingeestio stion n of labe abeled led orga rganic nic com compou pound) nd) 2000 mCi (inhalation of carbon monoxide) 200 mCi (inhalation of carbon dioxide) Sign up to vote on this title
Useful *[1.0 ALI = 2 mCi (ingested C- 14 organic compound) = 5,000 mrem CEDE] •
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Skin Skin Conta Contamin minati ation on Dose Dose Rate: Rate: 1090-1 1090-1180 180 mrem mrem per per 1.0 uCi/cm uCi/cm2 (7 mg/cm2 depth)
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RADIATION MONITORING DOSIMETERS
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• • • •
Not Not nee neede ded d (be (beta ta ener energy gy too too low low). ). 14C Beta Dose Rate: 6.32 rad/hr at 1.0 cm. in air per 1.0 mCi 14 C Skin Contamination Dose Rate: 13.33 mrad/hr per uCi on skin Dose Dose Rat Ratee from from a 1 mCi mCi isot isotro ropi picc poin pointt sour source ce of of 14C: Distance Rad/Hr 1 . 0 cm 12 41 . 4 2.0 cm 2 50 . 4 1 5. 2 c m 0.126 2 0. 0 c m 0.0046
GENERAL RADIOLOGICAL SAFETY INFORMATION
•
Urinal Urinalysi ysis: s: Not Requir Required; ed; howeve however, r, pruden prudentt after after a 14C radioactive spill or suspected intake.
•
Inhe Inhere rent nt vola volati tili lity ty (at (at STP STP): ): Not Not Sig Signi nifi fica cant nt..
•
Poss Possib ibil ilit ity y of orga organi nicc 14C compounds being absorbed through gloves.
•
Care Care shou should ld be take taken n NOT NOT to gene genera rate te 14CO2 gas which could be inhaled.
•
Internal Internal Dose is the concern: concern: Skin contamina contamination, tion, ingestion, ingestion, inhalation inhalation,, and and punctu puncture. re.
•
Always Always wear wear a lab lab coat coat and and dispos disposabl ablee gloves gloves when when work working ing with with 14C.
•
The concentr concentratio ation n of carbon carbon in adipose adipose tissue, tissue, including including the the yellow yellow marrow, marrow, is about about 3 times times the avera body concentration. No other organ or tissue of the body concentrates stable carbon to any significant exte
•
The fracti fractional onal absorp absorption tion of dietary dietary carbon carbon (uptake (uptake to blood) blood) is is usually usually in in excess excess of 0.90.
•
Three main classes of carbon compounds may be inhaled: inhaled: organic compounds, gases (CO or CO2), and ae of carbon containing compounds such as carbonates and carbides.
Organic Compounds - most organic compounds are NOT very volatile under normal circumstance probability of these being inhaled as vapors is therefore small. In circumstances where such substanc inhaled, it would be prudent to assume that once they enter the Sign respiratory system theytitle are instantaneous are up to vote on this completely translocated to the systemic circulation without changing their chemical form. Useful Not useful has been studied extensively. Since gas Gases - the inhalation of CO and its retention in body tissues relatively low solubility in tissue water, doses due to absorbed gas in tissues are insignificant in compa with doses due to the retention of CO bound to hemoglobin. CO2 in the blood exists mainly as a bicarbo
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CHROMIUM - 51
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[ 51 C r ] PHYSICAL DATA
Gamma Energy: X-ray Energy:
320 keV (9 (9.8% abundance) * 5 keV (22% abundance) *
*[Percent of disintegration resulting in this radiation being emitted]
No Betas Emitted Specific Ga Gamma Con Constant:
0.01 .017 mR mR/hr pe per mCi mCi at 1.0 1.0 meter
Physical Half-Life: Biological Half Life: Effective Half-Life:
27.8 days 616.0 days 26.6 days (w (whole body)
Specific Activity: Specific Activity (microspheres):
92,000 Curies/gram 63.56 mC mCi/gram
RADIOLOGICAL DATA
• • •
Critical Organ: Lower large intestine (LLI) Routes of Intake: Ingestion, inhalation, skin contact External External & interna internall exposur exposuree and conta contamina minatio tion n are radio radiolog logical ical concerns concerns..
Comm Commit itte ted d Dos Dosee Equ Equiv ival alen entt (CDE (CDE): ): (gonad & lung)
0.15 0.15 mrem mrem/u /uCi Ci (ing (inges este ted/ d/go gona nad) d) 1.41 mrem/uCi (inhalation/lung/Class W)
Comm Commit itte ted d Dose Dose Equi Equiva vale lent nt (CDE): (CDE):
1.20 1.20 mrem mrem/u /uCi Ci (ing (inges este ted/ d/GI GI trac tract/ t/LL LLI) I) 0.22 mrem/uCi (inhaled/LLI Wall/Class D)
Comm Commit itte ted d Effe Effect ctiv ivee Dose Dose Equ Equiv ival alen entt (CED (CEDE) E)::
Annual Limit on Intake (ALI)*:
0.10 0.107 7 mrem mrem/u /uCi Ci (in (inge gest sted ed)) 0.211 mrem/uCi (inhalation/Class D) 0.211 mrem/uCi (inhalation/Class W)
20 mCi (inhalation/Class W & Y) 52 mCi (inhalation/Class D/soluble) Sign up to vote on this title 40 mCi (ingestion) Useful Not useful
*[1.0 ALI = 40 mCi (51Cr ingested) = 5,000 mrem CEDE (Whole Body)]
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SURVEY INSTRUMENTATION
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• • •
Survey Survey meter meter equipped equipped with a NaI scintill scintillati ation on probe probe is recom recommend mended. ed. Survey Survey meter meter equipped equipped with with a G-M pancake/de pancake/detecto tectorr or standar standardized dized cylindric cylindrical al probe probe is very very inefficient detection of 51Cr (very low counting efficiency). efficiency). Smears Smears or wipes wipes counted counted in a liquid liquid scintill scintillation ation counter counter (indirect) (indirect) is best for the the detection detection of of removable surface contamination.
PERSONAL RADIATION MONITORING DOSIMETERS
Whole body & extremity badges required. REGULATORY COMPLIANCE INFORMATION
•
Derived Air Concentration (DAC): (inhalation)
2.0E-5 uCi/cc (Class D) 1.0E-5 uCi/cc (Class W) 8.0E-6 uCi/cc (Class Y)
•
Airb Airbor orne ne Effl Efflue uent nt Rele Releas asee Limi Limit* t*::
6.0E 6.0E -8 uCi/cc (Class D) 3.0E-8 uCi/cc (Class W & Y)
*
Applicable Applicable to to the assessment assessment & control of dose to the the public public (10 (10 CFR 20.1302). If this this concentrat concentration ion wa continuously for over one year the resulting TEDE would be 50 mrem.
•
Urinalysi Urinalysiss : Not required; required; however, however, may may be be request requested ed in in the the event event of a spill spill of 51Cr.
•
Whole Whole Body Body Bioa Bioassa ssay: y: May be prud prudent ent in the the even eventt of a suspe suspecte cted d intak intakee of 51Cr through ingestion, inha skin absorption, or a wound.
•
Gamm Gammaa (pho (photo ton) n) exp expos osur uree rate ratess from from 1.0 1.0 mCi mCi 51Cr point source: Distance 1.0 cm 5.0 cm 1 0. 0 c m 100.0 cm
•
mrad/hr. 160.0 6.4 1. 6 0 . 0 16
Inhere Inherent nt Volati Volatilit lity y (STP): (STP): Insign Insignifi ifican cant/N t/Negl egligi igible ble
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HYDROGEN - 3
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[3H] PHYSICAL DATA
•
Beta Energy:
• • •
Physical Half-Life: Biological Half-Life: Effective Half-Life: *
• • • •
18.6 keV (maximum) 5.7 keV (average) (100% abundance) 12.3 years 10 - 12 days 10 - 12 days *
Forcing Forcing liquid liquidss to toleranc tolerancee (3-4 liter liters/da s/day) y) will reduc reducee the effect effective ive half-l half-life ife of 3H by a factor of 2 or 3. (Rela flush out of system with fluids.)
Specific Activity: Maximum Beta Range in Air: Maximum Beta Range in Water: Penetrability in Matter or Tissue:
9640 Ci/gram 6 mm = 0.6 cm = 1/4" 0.006 mm = 0.0006 cm = 3/10,000" Insignificant*
*[0% of beta particle energy transmitted through dead layer of skin]
RADIOLOGICAL DATA
• • • • •
Leas Leastt rad radio ioto toxi xicc of of all all radi radion onucl uclid ides es Crit Critic ical al Orga Organ: n: Body Body Wate Waterr or Tiss Tissue ue Routes of Intake: Intake: Ingestion, Ingestion, Inhalation, Inhalation, Puncture, Puncture, Wound, Skin Contaminat Contamination ion (Absorption (Absorption)) Exte Extern rnal al expo exposu sure re from from weak weak 3H beta energy - not a radiological concern Interna Internall exposur exposuree & conta contamin minatio ation n are primary primary radiolog radiologica icall concern concernss
•
Commit Committed ted Dose Dose Equiva Equivalen lentt (CDE): (CDE):
•
Commit Committed ted Effect Effective ive Dose Dose Equiva Equivale lent nt (CEDE) (CEDE):: 90 mrem/m mrem/mCi Ci (inges (ingested ted)) 63 mrem/mCi (inhaled)
•
Annual Annual Limit Limit on Intake Intake (ALI)* (ALI)*:: 80 mCi (inges (ingestio tion n or inhala inhalatio tion) n) [ 3H2O]
64 mrem/ mrem/mCi mCi (inges (ingested ted)) 64 mrem/mCi (inhaled) 64 mrem/mCi (puncture)
* [1.0 ALI = 80 mCi (3H) = 5,000 mrem CEDE]
•
Sign up to vote on this title Skin Skin Contam Contamina inatio tion n Expos Exposure ure Rate: Rate: 57,900 57,900 mrad mrad/hr /hr/mC /mCii (cont (contact act)* )* Useful Not useful * Exposure rate to dead layer of skin only * Skin contamination of 1.0 uCi/cm 2 = 0 mrad/hr dose rate to basal cells cells
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RADIOACTIVE WASTE
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•
Solid, liquids, scintillation vials, pathological materials, animal carcasses
REGULATORY COMPLIANCE INFORMATION
•
Deri Derive ved d Air Air Conc Concen entr trat atio ion n (DA (DAC) C) :
•
Airborne Effluent Release Limit: *
2.0 2.0 E-5 uCi/cc (occupational) 1.0 E -7 uCi/cc *
[Applicable to the assessment & control of dose to the public (10 CFR 20.1302). If this concentration was continuously for over one year the resulting TEDE would be 50 mrem.]
•
Contro Controlle lled d Area Area Remova Removable ble Contam Contamina inatio tion n Limit Limit:: 2,200 2,200 dpm/1 dpm/100 00 cm cm 2
•
Urin Urinal alys ysis is (By (Bypr prod oduc uctt Lice Licens nse) e):: Required when handling ≥ 100 mCi 3H
GENERAL RADIOLOGICAL SAFETY INFORMATION
•
Inhe Inhere rent nt Vola Volati tili lity ty (at (at STP) STP):: SUBSTANTIAL
•
Experimen Experimental tal uses uses include include:: total total body water water measur measurement ementss & in-vivo in-vivo labeli labeling ng of prolife proliferator ratory y cells cells by inj tritium-labeled compounds compounds (i.e., thymidine). Tritium labeling is also also used in a variety of metabolic studi
•
Oxidation of 3H gas in air is usually slow (< 1% per day).
•
Absorption of 3H inhaled in air is much less when it is present as elemental 3H than as tritiated water (HT
•
Tritium Tritium penetra penetrates tes the the skin, skin, lungs, lungs, and GI tract tract either either as tritiate tritiated d water or or in the gaseous gaseous form. form.
•
As ga gaseous hy hydrogen, 3H entering the lung or GI tract is completely absorbed and rapidly dispersed within
•
Some 3H is incorporated into cellular components and has a long turnover rate.
•
Forcing Forcing fluids fluids reduces reduces integra integrated ted interna internall expos exposures ures from 3H.
•
Monitor for 3H contamination using only wipe-testing (bench tops, floors, refrigerator/freezer refrigerator/freezer handles, pho
•
Always Always wear wear a lab lab coat coat & dispo disposab sable le glov gloves es when when handli handling ng 3H.
• •
Skin contami contaminatio nation, n, inhalation inhalation,, ingestion, ingestion, or absorpt absorption ion through through the the skin skin is assumed assumed to to be complete completely ly and instantaneously absorbed and rapidly mixed with total body water. The volume volume of tota totall body body wate waterr (stan (standar dard d man) man) is is 42,00 42,000 0 ml. ml. Sign up to vote on this title
•
Useful total Not useful The co concentration of of 3H in urine is assumed to be the same as in body water.
•
Detection li limit of of 3H in urine:
1.08E-5 uCi/ml (approximately)
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IODINE - 125
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[ 1 25 I ] PHYSICAL DATA
•
Gamma Energies: (No (No beta betass emit emitte ted) d)
35.5 keV 27.0 27.0 keV keV 27-32 keV 31.0 keV
(7% abundance/93% internally converted, gamma) (113 (113%, %, x-ra x-ray) y) (14%, x-ray) (26%, x-ray)
•
Specific Gamma Ray Constant: 0.27 to to 0. 0.70 mR mR/hr pe per mC mCi at at 1 meter (Current literature indicates 0.27 mR/hr per mCi at 1 meter)
• • •
Physical Half-Life: Biological Ha Half-Life: Effective Half-Life:
60.1 days 120-138 da days (u (unbound io iodine) - thyroid el elimination 42 days (unbound iodine) - thyroid gland
• •
Specific Activity: Intrinsi nsic Specific Act Activity:
17,400 Ci/gm (theoretical/carrier free) 22.0 2.0 Ci/ Ci/millimole
RADIOLOGICAL DATA
• • •
Critic Critical al Organ Organ (Biolo (Biologic gical al Destin Destinati ation) on):: Thyroi Thyroid d Routes Routes of Intake Intake:: Ingestion, Ingestion, inhalation inhalation (most probable), probable), puncture, puncture, wound, wound, skin skin contam contaminati ination on (absorp (absorption tion 125 External External and inter internal nal exposu exposure re and and contam contaminati ination on concern concernss exist exist in use use of I
•
Committed Do Dose Eq Equivalent (C (CDE): (Organ Doses)
814 mr mrem/mCi (t (thyroid/inhalation/class "D "D") 1185 mrem/mCi (thyroid/ingestion/NaI form) 910 mrem/mCi (thyroid/inhalation) 1258 mrem/mCi (any organ/puncture/adult)
•
Commit Committed ted Effect Effective ive Dose Dose Equiva Equivalen lent( t(CED CEDE): E):
24 mrem/ mrem/mCi mCi (whole (whole body/i body/inha nhalat lation ion))
SHIELDING
• •
Lead Lead foil foil or or sheet sheetss (1/32 (1/32 to 1/16 1/16 inch inch thick thick): ): 0.152 0.152 mm lead lead foil foilSign up to vote on this title Half Half Value Value Laye Layer: r: 0.02 0.02 mm = 0.00 0.008 8 inc inche hess Useful Not useful
SURVEY INSTRUMENTATION
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•
Indi Indivi vidu dual alss who who will will be usin using g 125 I in the NaI or KI chemical form are required to obtain a thyroid scan used as a baseline reference prior to use.
•
The thyroi thyroid d gland gland accumula accumulates tes 20 - 30% of the the soluble soluble radioi radioiodine odine taken taken in by the body. body. All radioi radioiodine odine body can be assumed to be eliminated quite rapidly via the urine.
•
Thyroid Bi Bioassay is is required by law when handling > 1 mCi in the 125 I in the sodium or potassium chemical form. In accordance with the NRC license and MSU's commitment to ALARA, the threshold a is taken to be 0.1 mCi. The thyroid scan is to be obtained not less than 24 hours but not more than one after the handling or use of that quantity and form of 125 I. In addition, all workers who assist or obse manipulations of the above quantity and type of 125 I, or are sufficiently close to the process so that int possible (within a few meters and in the same room) are required to obtain thyroid scans under the conditions listed above.
•
Fume hood sash glass provides provides adequate adequate shielding shielding for for most most iodinat iodinations. ions. Extra shielding shielding is is not recom since it impedes air flow into the hood.
•
Shielding Shielding is not not required required for for most uses uses of this this nuclide nuclide due to to the low energy energy and and low amounts amounts typica typically lly use
•
Use a cannu cannula la adapte adapterr needl needlee to vent vent stock stock vials vials of of 125I used for iodinations. iodinations. This prevents puff releases. releases.
•
Segreg Segregate ate waste waste from from iodi iodinat nation ionss (free (free)) from from othe otherr (bound (bound)) 125 I waste and store it in the fume hood, in t sealed ziplok bags (solid waste) or screw top containers (liquid (liquid waste) until waste pickup.
•
Cover test test tubes tubes used to to count or or separate separate fractio fractions ns from iodina iodinations tions with with parafilm parafilm or or other tight tight caps caps to p release while counting or moving outside the fume hood.
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PHOSPHORUS - 32
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[ 32 P ] PHYSICAL DATA
•
Beta energy:
1.709 MeV 0.69 0.690 0 MeV MeV
(maximum) (average, 100% abundance)
• • •
Physical half-life: Biological half-life: Effe Effect ctiv ivee hal halff-li life fe::
14.3 days 1155 days 14.1 14.1 days days (bon (bone) e) / 13. 13.5 5 day dayss (wh (whol olee bod body) y)
•
Specific activity:
285,000 Ci/gm
• • • •
Maximum range in air: Maximum range in water/tissue: Maximum range in Plexiglas/lucite/plastic: Half-Value Layer (HVL):
610 cm = 240 inches = 20 feet 0.76 cm = 1/3 inch 0.61 cm = 3/8 inch 2.00 mm (water/tissue)
RADIOLOGICAL DATA
• • • •
Critic Critical al orga organ n (biolo (biologic gical al dest destina inatio tion) n) (sol (solubl ublee forms forms): ): Bone Bone Critic Critical al orga organs ns (inso (insolub luble le form formss or non-t non-tran ranspo sporta rtable ble 32P compounds): Lung (inhalation) and G.I. tract/l large intestine (ingestion) Routes of intake: intake: Ingestion, Ingestion, inhalation inhalation,, punctur puncture, e, wound, skin contaminati contamination on (absorptio (absorption) n) 32 Exte Extern rnal al and and int inter erna nall exp expos osur uree fro from m P
•
Committed Dose Equivalent (CDE): (Organ Doses)
•
Commi Committe tted d Effect Effective ive Dose Dose Equiv Equivale alent nt (CEDE) (CEDE):: 7.50 7.50 mrem/ mrem/uCi uCi (inge (ingest sted/ ed/WB) WB) 5.55 mrem/uCi mrem/uCi (inhale/Class D) 13.22 mrem/uCi mrem/uCi (inhale/Class W) Skin Skin contam contamina inatio tion n dose dose rate: rate: 8700-9 8700-9170 170 mrem/u mrem/uCi/ Ci/cm cm 2 /hr. (7 mg/cm2 or 0.007 cm depth in tissue). Dose Dose rate rate to basal basal cell cellss from from skin skin cont contami aminat nation ion of of 1.0 uCi/cm uCi/cm2 (localized dose) = 9200 mrad/hr. Bone receives receives approxima approximately tely 20% of the the dose dose ingeste ingested d or inhal inhaled ed for for soluble soluble 32P compounds. Sign up to vote on this title Tissues Tissues with with rapid rapid cellular cellular turnov turnover er rates rates show highe higherr retention retention due due to concent concentrati ration on of phosphor phosphorous ous in t Useful Not useful nucleoproteins. 32P is eliminated from the body primarily via urine. Phos Phosph phor orus us meta metabo boli lism sm;; see see 33P Fact Sheet.
• • • • • •
32 mrem/uCi (ingested) 37 mrem/uCi (puncture) 96 mrem/uCi (inhaled/Class W/lungs) 22 mrem/uCi (inhaled/Class D/bone marrow)
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DOSE RATES (from unshielded 1.0 mCi isotropic point source)
Distance 1.00 cm 15.24 cm 10.00 ft • •
Rads/hr 348 1. 49 0. 0 0 1 5
78,0 78,000 00 mrad mrad/h /hrr at at sur surfa face ce of 1.0 1.0 mCi mCi 32P in 1 ml liquid. 26,000 26,000 mrad mrad/hr /hr at mouth mouth of open open vial vial cont contain aining ing 1.0 mCi 32P in 1.0 ml liquid.
GENERAL PRECAUTIONS
•
Because Because it is a bone seeker, seeker, special special precautions precautions must be taken taken to to minimiz minimizee any chance of introdu introducing cing body.
•
Airborn Airbornee contamin contaminati ation on can be genera generated ted throug through h drying drying (dust), (dust), rapid rapid boiling, boiling, or expell expelling ing solut solution ionss th syringe needles and pipette tips, due to aerosols.
•
Pers Personn onnel el rad radia iati tion on moni monito tors rs (whol (wholee body body and fin finger ger rin rings gs)) are required when handling > 1.0 mCi of any time.
•
Never Never work work direct directly ly over over an open open conta container iner;; avoid avoid direct direct eye eye expos exposure ure from penetrat penetrating ing 32P beta particles.
•
Always Always wear wear a lab coat coat and and dispos disposabl ablee glov gloves es when when hand handli ling ng 32P.
•
Monito Monitorr personn personnel el work work areas areas and floor floorss using using a GM survey survey meter meter equip equipped ped with with a pancak pancakee (beta) (beta) pro surface contamination.
•
Monito Monitorr for remova removable ble surf surface ace contam contamina inatio tion n by smea smearin ring g or wipi wiping ng where where 32P is used.
•
Use lowlow-den densi sity ty (low (low atom atomic ic numbe number) r) shie shieldi lding ng mate materia riall to shiel shield d 32 P and reduce the generati Bremsstrahlung x-rays. The following materials are low atomic number materials: Plexiglas, acrylic, plastic, wood, or water.
•
Do NOT use lead lead foil foil,, lead lead sheets sheets,, or other other high high dens density ity mate materia rials ls (met (metals als)) to shie shield ld 32 P directly. SignNOT up tobe vote on this title with atomic number higher than that of aluminum (Z = 13) should used. Penetrating Bremsstra x-rays will be generated in lead and other high density shielding material. Useful Not useful
•
Safety Safety glasse glassess or or gogg goggles les are recom recommen mended ded when when work working ing with with 32P.
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PHOSPHORUS - 33
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[ 33 P ] PHYSICAL DATA
•
Beta energy:
0.249 MeV (maximum, 100% abundance) 0.085 MeV (average)
• • • •
Physical half-life: Biolog Biologica icall halfhalf-lif life: e: Effective half-life: Specific activity:
25.4 days 19 days days (40% (40% of int intake ake;; 30% rapi rapidly dly elim elimin inate ated d from from body, body, rema remaini ining ng 30% 30% decays decays 24.9 days (bone) 1,000 - 3, 3,000 Ci Ci/millimole
• • • •
Maximum beta range in air: Maximum range in water/tissue: Maximum range in plexiglas/lucite/plastic: Half-Value Layer (HVL):
89 cm = 35 inches = 3 feet 0.11 cm = 0.04 inch 0.089 cm = 0.035 inch 0.30 mm (water/tissue)
RADIOLOGICAL DATA
• • • • • • • • • •
Crit Critic ical al orga organ n (bi (biol olog ogic ical al dest destin inat atio ion) n) (sol (solub uble le form forms) s):: Bone Bone marr marrow ow 33 Crit Critic ical al org organ anss (ins (insol olub uble le for forms ms or or nonnon-tr tran ansp spor orta tabl blee P compounds): Lung (inhalation) and G.I. tract/ large intestine (ingestion) Rout Routes es of inta intake ke:: Inge Ingest stio ion, n, inha inhala lati tion on,, pun punct ctur ure, e, woun wound, d, skin skin cont contam amin inat atio ion n (ab (abso sorp rpti tion on)) Interna Internall expos exposure ure and contami contaminat nation ion are the primary primary radiolog radiological ical concern concernss Comm Commit itte ted d Dose Dose Equi Equiva vale lent nt (CDE (CDE): ): 0.5 0.5 mrem mrem/m /mCi Ci (inh (inhal alat atio ion) n) 2 Skin Skin cont contam amin inat atio ion n dos dosee rat rate: e: 2,910 2,910 mrem mrem/h /hr/ r/uC uCi/ i/cm cm (7 mg/cm2 or 0.007 cm depth in tissue) Fraction of 33P beta particles transmitted through the dead skin layer is about 14%. Tissues Tissues with with rapid rapid cellul cellular ar turnove turnoverr rates rates show show higher higher retent retention ion due due to concen concentrat tration ion of phosp phosphoru horu nucleoproteins. 33P is eliminated from the body primarily via urine. Phos Phosp phor horus metab etabol oliism: sm: 30% 30% is rapid apidlly eli elimina minatted from from body ody 40% has a 19-day biological half-life 60% of 33P (ingested) is excreted from body in first 24 hrs
SHIELDING
•
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Useful Not useful Not require required; d; however however low densi density ty material material is recomme recommended, nded, e.g., e.g., 3/8 inch inch thick thick plexigla plexiglas, s, acrylic, acrylic, lucite, lucite, plastic or plywood.
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SULFUR - 35
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[ 35 S ] PHYSICAL DATA
•
Beta energy:
167 keV (maximum) 53 keV (average) (100% abundance)
• • •
Physical Half Life: Biological Half Life: Effective Half Life:
87.4 days 623 days (unbound 35S) 44 - 76 days (unbound 35S)
•
Specific Activity:
42,400 Ci/g
• • •
Maximum Beta Range in Air: Maximum Beta Range in Water or Tissue: Maximum Beta Range in Plexiglas or Lucite:
•
Fraction of 35S betas transmitted through dead layer of skin = 12%
26.00 cm. = 10.2 in. 0.32 mm. = 0.015 in. 0.25 mm. = 0. 01 in.
RADIOLOGICAL DATA
• • • •
Cri Critic tical orga organ: n: Tes Testi tiss Routes Routes of Intake: Intake: Ingestion, Ingestion, inhalation inhalation,, puncture puncture,, wound, wound, skin contaminat contamination ion (absorptio (absorption) n) 35 Exte Extern rnal al exp expos osur uree (dee (deep p dose dose)) from from wea weak k S beta particles is not a radiological concern. Interna Internall exposur exposuree and conta contamin minatio ation n are the the primar primary y radiolog radiologica icall concerns concerns..
•
Committed dose equivalent (CDE):
•
Committed Ef Effective Do Dose Eq Equivalent (C (CEDE):
•
Annual Limit on Intake (ALI)*:
10.00 mrem/uCi (ingested) 0.352 mrem/uCi (puncture) 2.6 mr mrem/uCi (i (ingested)* *(Assumes a 90 day biological half life) 10 mCi (ingestion of inorganic 35S compounds 6 mCi (Ingestion of elemental 35S) 8 mCi (ingestion of sulfides or sulfates/LLI)** 10 mCi (inhalation of 35S vapors) 20 mCi (inhalation of sulfides or sulfates) up to vote on this title 35S) 2 mCiSign (inhalation of elemental Useful Not useful
*1.0 ALI = 10 mCi (inhaled 35S vapors) = 5,000 mrem CEDE ** 1.0 ALI = 8 mCi (ingestion sulfides/sulfates LLI) = 50,000 mrem CDE
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RADIATION MONITORING DEVICES
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•
(Badges): Not needed, because 35S beta energy is too low, and is not an external radiation hazard
•
Dose Dose Rate Rate from from a 1 millic millicuri uriee unshie unshielde lded d isotro isotropic pic poin pointt source source of of 35S: Distance 1.0 cm 2.5 cm 15.24 cm 20.00 cm
Rad/hr 1 1 7 3. 6 93 .7 0.2 0. 01
GENERAL RADIATION SAFETY INFORMATION
• • • • • •
•
• • • • •
Urinalysis Urinalysis:: Not required required,, but may be be requested requested by Health Health Physics Physics staff after a spill spill or person personnel nel contam contam 35 involving S. Inhe Inhere rent nt vol volat atil ilit ity y (STP (STP): ): SIGNIFICANT for 35 S methionine and cysteine. 35 Radiolysis of S amino acids (cysteine and methionine) during storage and use may lead to the relea volatile impurities. Volatile impurities are small ( ≤ 0.05%). Metabolic Metabolic behavior behavior of of organic organic compounds compounds of sulfur sulfur (cysteine (cysteine and methionine methionine)) differs differs considerabl considerably y fro metabolic behavior of inorganic compounds. Organic compounds compounds of of sulfur sulfur (cysteine (cysteine and methion methionine) ine) become incorporated incorporated into various metabolites. metabolites. sulfur entering the body as an organic compound is often tenaciously retained. The fraction fractional al absorptio absorption n of sulfur sulfur from from the the gastrointes gastrointestinal tinal tract is typically typically > 60% for for organic organic compou compou sulfur. Elemental sulfur is less well absorbed from the GI tract than are inorganic compounds of the (80% for all inorganic compounds and 10% for sulfur in its elemental form). Elemental sulfur is an inhalation Class W (meaning it is retained for weeks in the body). Inhal nhalat atio ion n of of the the gase gasess SO SO 2, COS, H2S, and CS2 must be considered. Sulfur entering the the lungs in these is completely and instantaneously translocated to the transfer compartment; from there, its metabolism same as that of sulfur entering the transfer compartment following ingestion or inhalation of any other or compound of sulfur. Contamination Contamination of internal internal surfaces of storage storage and reaction reaction vessels may occur occur (rubber (rubber stoppers, gasket rings). Vials of 35 S labeled cysteine and methionine should be opened and used in ventilated enclosures (ex hoods). The The vola volati tile le comp compon onen ents ts of 35S labeled amino acids should be opened and used in ventilated enclosures (e hoods). Sign up to vote on this title 35 The The vola volati tile le comp compon onen ents ts of S labeled cysteine and methionine are presumed to be hydrogen sulfide (H Useful Not useful methyl mercaptan (CH 3SH), respectively. 35S vapors may be released when opening vials containing labeled amino acids, during any incubating of c or cells containing 35S, and the storage of 35S contaminated wastes.
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Directions for Conducting a Radiation Safety Surve
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Radiation safety surveys must be conducted on a weekly to monthly basis in each laboratory w radioactive materials are used. Appropriate detection equipment must be used for each nu monitored. Examples are as follows: 3H
Beta
.015 MeV
Liquid Scintillation Counter (Wipe Samples)
14C
Beta
.156 MeV
Geiger Counter with Beta Pancake Probe
35S
Beta
.168 MeV
Geiger Counter with Beta Pancake Probe
33P
Beta
.228 MeV
Geiger Counter with Beta Pancake Probe
32P
Beta
1.71 MeV
Geiger Counter with Beta Pancake Probe
125I
Gamma
.035 MeV
Geiger Counter with Low Energy Gamma Probe
51Cr
Gamma
.320 MeV
Geiger Counter with Low Energy Gamma Probe
1.
Use a Geiger Geiger counter counter rather rather than than liquid liquid scintill scintillatio ation n counter counter for monitor monitoring ing all nucli nuclides des e 3H. Geiger counters detect both removable and non-removable contamination, contaminatio n, whereas and liquid scintillation counting detect only removable contamination. 3H cannot be det by any Geiger counter, so liquid scintillation counting is the only method to co nduct a s for that nuclide.
2.
You must must survey survey in all areas areas where where radiois radioisotopes otopes are used, used, stored stored or or disposed, disposed, and th adjacent to those areas. This includes centrifuges, centrifuges, incubators, cold rooms, sealing equip pipetters and any other equipment which has been used for radioisotope work.
3.
Make a record record of all labora laboratory tory surveys. surveys. The record record should should include include a map map of the the room, room, m to identify where you surveyed, nuclides surveyed for, equipment identification, backgr of the equipment, efficiency for each nuclide monitored, results oftitle the survey. Sign upand to vote on this include area of contamination, nuclide, CPM reading, DPM, uCi amount and corrective a Useful beused: Not useful should taken. To convert CPM to uCi, the following equation CPM/Efficiency = DPM
DPM/2 22 E6 = uCi amount
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To monitor monitor all other other radioisot radioisotopes, opes, use a Geiger Geiger counter counter with the correc correctt probe. probe. Follow Follow steps: a. b. c. d. e.
f. g. h. i.
Turn Turn the the meter meter on and and firs firstt check check the batter batteries ies by looki looking ng at at the the batte battery ry check check read the batteries are low, replace them before surveying. surveying. You may survey with the aud or off. However, significant rate changes are easily detected by the audio. Set the the meter meter to read read on on the lowest lowest possi possible ble sett setting ing,, e.g., e.g., .1X .1X or 1X 1X the the count count rate rate the response to fast response. Check Check and recor record d the the backgr backgroun ound d read reading ing.. (Note (Note:: Fast Fast res respon ponse se mode mode give givess a background range, which is needed to determine when contamination is present.) Slowly Slowly scan the area to be surve surveyed yed with the probe. probe. Hold the probe probe about about half an i above the areas to maximize detection. If the the needle needle reads reads above above twice twice (rule (rule of thumb thumb for surveyin surveying) g) backgr background, ound, switch switch response to slow response to accurately quantify the contamination. Check the suspected source of contamination from more than one direction to confirm the sour the response. The meter response may be due to waste, samples or other radioactiv materials in the area, not to contamination. Reco Record rd the the res resul ults ts of the the sur surve vey y on on the the rec recor ord d for form. m. Deconta Decontamin minate ate or disp dispose ose of the the cont contami aminat nation ion in the the radi radioact oactive ive waste. waste. If the contaminated area or equipment cannot be decontaminated, shield and label the contamination with the nuclide, date and activity in DPM or uCi. Remem Remember ber to tur turn n the the mete meterr off off afte afterr each each use use to to save save batt batter erie ies. s. If major contamination is found, report immediately to the principal investigator.
SURVEY FREQUENCY GUIDE A m o u n t U se d
Do cu me nte d S ur v ey Fr e qu en c
Always less than 200 uCi in shipment
Monthly
≥
After eac h use of ≥ 200 uCi (means e
200 uCi in shipment
up to vote on this title handlingSign of shipment, even if using much
Useful useful Not than 200uCi), but not more than one per we
unless ORCBS deems otherwise (certain h
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IODINATION SAFETY TIPS
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Revised June, 1995
Iodinations are performed commonly at MSU; however, with safe practices exposur not occur. Air monitoring may be done during iodinations by ORCBS to assure that room not contaminated. Additionally, bioassays bioassays detect any uptakes which may occur. These bioa are required for all workers performing iodinations. Iodination labeling, however, can create potential exposures to the thyroid in wo performing iodinations if proper safety precautions are not followed explicitly. 125I in the N chemical form is volatile, volatile, and exposure through inhalation routes routes can occur. Most iodination done with quantities of 1.0 mCi or greater, so very little airborne release of this concent material may cause a significant 125I uptake. The following list of safety precautions will assist workers in preventing unnece exposures to 125I during iodinations. If you have questions, or would would like assistance in iodi procedures, please call 5-0153. 1.
2. 3. 4. 5. 6.
7.
All All io iodina dinattions ons an and us use of of Na Na12 5 I must be conducted in a fume hood certifie radioisotope use. Work should be done at least 6 inches back from the front of the hood. Fume hoods should be free of clutter, and large objects should be placed on b to elevate them 2 inches from from the floor of the the fume hood. The sash of the fume should be brought down to the lowest possible height while still maintaining ample for manual dexterity. The fume hood should should be be covered covered with with poly-b poly-backed acked absorben absorbentt paper paper to absor absorb b po spills, drips or airborne activity. Double Double glov gloves es shou should ld be be worn. worn. Latex Latex or N-Dex N-Dex glov gloves es are are pref prefera erable ble beca because use they they h tighter fit, allowing good dexterity while wearing two or three pairs. Poly-b Poly-back acked ed absorb absorbent ent pape paperr should should be be taped taped to the the floor floor in in front front of the the fume fume ho prevent contamination and spreading in the event of an accidental spill or release. Lab Lab coa coats ts and and fil film m bad badge gess mus mustt be be wor worn. n. A GM rate rate meter meter with with a low low energ energy y gamma gamma probe probe must must be used used during during the the iodi iodinati nati should be placed near the iodination hood (not inside the hood) with the audio o noticeable and substantial change in the audible count rate during the iodination indicator that will alert the worker to possible release from the fume hood. Proce should then be implemented to prevent further release into the breathing airin the r Sign up to vote on this title Call the ORCBS for advice on handling the situation. useful a conduit fo anUseful To remove the Na125I from the shipping vial, use adaptertoNot provide syringe used to withdraw the aliquot. A short 16 gauge cannula needle, available General Stores, makes an excellent adapter. This prevents the syringe needles
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12. 13.
14. 14 . 15.
RADIATION SAFETY
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the iodination is finished, place both dry and liquid waste in double ziplok plastic bags label the waste with radioactive waste tags. Denote "Free 125I" on the waste tag. Store Store all syringes syringes,, glassware glassware and and other equipm equipment ent that that is reused reused in the the iodinatio iodinatio hood between uses. Label all iodination equipment thoroughly. Thyroid Thyroid scans scans must must be perfo performed rmed on workers workers after after each iodinati iodination. on. A baselin baselinee th scan is done to determine a background for each iodinater prior to conducting iodinatio MSU. Post-iodination thyroid scans are done no less than 24 hours after the iodin and no longer than 1 week after the iodination. Thyroid scans are required required by law, an obtaining them may cause a violation of our NRC license conditions. Call the ORC obtain a thyroid scan. If a spill spill occurs occurs insid insidee the fume fume hood during during an iodinat iodination, ion, close close the the hood sash sash comp If a spill occurs outside the fume hood, place absorbent on the spill and evacuate pers from the room. Call the ORCBS immediately to notify that the spill has occurred. After every iodinat iodination, ion, thoroug thoroughly hly survey survey the the entire entire area, area, including including floors floors equipment, outer waste container surfaces, hands, feet and clothing. 12 5I ACCIDENT EMERGENCY PROCEDURES FOR FREE 125
In the event of an accident with with free iodine outside the hood, don't panic. Immediatel everyone out of the room. If possible, grab the rate meter on your way out. To minimiz spread of contamination, the people involved should go to a single, pre designated locatio close the door. (A desirable location would have available a telephone, sink, hood and "low traffic" area. The hallway outside the room may be the only choice if there are no ad rooms with closing doors.)
It is recommended that some disposable lab matting or other absorbent paper be placed on the for people to stand on, until they can be surveyed and found free of contaminatio decontaminated. decontamina ted. If you have any contamination on your skin, wash it off. If your cloth contaminated, remove the affected articles and place in the hood. Be sure the hood is turned o
During regular work days and hours call the ORCBS at 5-0153 and request to speak to a h physics staff staff member. Tell the person answering answering the phone that you you are reporting a rad emergency. Then call your PI and let him/her know exactly what has happened and what you done thus far. Sign up to vote on this title
If an accident occurs after regular working hours, dial 911, tell the Useful Not useful that you ha dispatcher radiation emergency emergency and need Radiation Safety assistance. assistance. (They will call the ORCBS emer pager.) Be prepared to provide the following information:
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LABORATORY CLASSIFICATION TABLE
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RADIONUCLIDES CLASSIFIED ACCORDING TO RELATIVE RADIOTOXICITY PER UNIT ACTIVITY*
Group I:
Very high radiotoxicity
210Pb
226Ra
227Th
231Pa
233U
238Pu
241Pu
243Am
244Cm
249Cf
210Po
228Ra
228Th
230U
234U
239Pu
242Pu
242Cm
245Cm
250Cf
223Ra
227Ac
230Th
232U
237Np
240Pu
241Am
243Cm
246Cm
252Cf
Group II:
High radiotoxicity
22Na
56Co
95Zr
124Sb
126I
140Ba
170Tm
207Bi
228Ac
36Cl
60Co
106Ru
125Sb
131I
144Ce
181Hf
210Bi
230Pa
45Ca
89Sr
110Ag
127Te
133I
152Eu
182Ta
211At
234Th
46Sc
90Sr
115Cd
129Te
134Cs
154Eu
192Ir
212Pb
236 U
54Mn
91Y
114In
124I
137Cs
160Tb
204Tl
224Ra
249Bk
Group III:
m
m
m
m m
Moderate radiotoxicity radiotoxicity
7Be
48Sc
65Zn
91Sr
103Ru
125Te
140La
153Gd
183Re
14C
48V
69Zn
90Y
105Ru
127Te
141Ce
159Gd
186Re
18F
51Cr
72Ga
92Y
106Rh
129Te
24Na
52Mn
73As
93Y
103Pd
131Te
197Hg Sign up165 toDy vote on this 143Ce 188 Retitle 197Hgm 142 Useful 166 Not 185useful 203
Pr
Dy
Os
38Cl
56Mn
74As
97Zr
109Pd
132Te
143Pr
166Ho
191Os
m
m
m
199Au
Hg
200Tl
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Group IV:
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Low radiotoxicity
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3H
58Co
71Ge
87Rb
97Nb
103Rh
129I
15O
59Ni
85Kr
91Y
96Tc
113In
37A
69Zn
85Sr
93Zr
99Tc
125I
m
m
m
m
m m
m
134Cs
187Re
197Pt
131Xe
135Cs
191Os
232Th
135Xe
147S
193Pt
NatTh
m
m
m
m
m
m
* From Safe Handling of Radionuclides, IAEA Safety Standards, 1973
TABLE II: LIMITATION ON ACTIVITIES IN VARIOUS TYPES OF WORK PLACE OR LABORATORY*
Radiotoxicity
Minimum
o f
significant
radionuclides
quantity (uCi)
Ty p e C
Type B
Typ
1. Very high
0 .1
10 uCi or less
10 uCi - 10 mCi
10 mC
2. Hi High
1.0
100 uCi or less
100 uCi - 100 mCi
100 mC
3. Moderate
1 0 .0
1 mCi or less
1 mCi - 1 Ci
4 . L ow
100.0
10 mCi or less
10 mCi - 10 Ci
1 Ci o 10 Ci
Type C, Type B and Type A have the meanings normally used in the classification of labora Sign upchemical to vote on laboratory. this title for handling radioactive radioactive materials. Type C is a good quality Type B specially designed radioisotope radioisotope laboratory. Type A is a specially laboratory for han Usefuldesigned Not useful large activities of radioactive radioactive materials. In the case of a conventional modern chemical labor with adequate ventilation and fume hoods, as well as polished, easily cleaned, non-abso surfaces, etc., it would be possible to increase the upper limits limits of activity for for Type C labora
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CHECKLIST FOR TRAINING WORKERS IN RADIATION LABORATORI Effective 5/3/93, Revised 6/1/95
The following is a list of information which should be reviewed by the principal investigator all individuals frequenting any work area where there are radioactive materials. Please write a No, or NA (Not Applicable) in the box provided next to the training item. 1. 2. 3. 4. 5.
Right Right to Know Know Traini Training ng has has been been comple complete ted. d. ORCBS ORCBS Radi Radiati ation on Safety Safety Traini Training ng has been complet completed. ed. ORCBS ORCBS Chemic Chemical/ al/Bio Biolog logica icall Safety Safety Train Training ing has has been comp complet leted. ed. ORCBS ORCBS Bloodb Bloodborne orne Pathogen Pathogen Training Training has been complet completed. ed. The exposur exposuree limits limits for radiat radiation ion have have been been reviewed reviewed with the worker worker (Refer (Refer to instruction sheet for table). 6 . Radiatio Radiation n warning warning symbols symbols and and their their meanin meanings gs have have been been reviewe reviewed d with with the worker. 7 . The locati locations ons of radioa radioacti ctive ve material materials, s, hazardou hazardouss chemicals chemicals and and biohazard biohazardous ous agents present in the laboratory have been pointed out to the worker. 8 . The relat relative ive risks risks of of being being near to or or using using the hazard hazardous ous agent agentss present present in the the laboratory have been reviewed with the worker. 9. The locat location ion and and types types of waste wastess and conta container inerss for the the wastes wastes have have been been identified with the worker. 10. 10 . The proper procedures procedures for emergenc emergencies ies which which may arise arise in the laboratory laboratory have have been reviewed with the worker. This information includes the location of emergency spill kits, emergency response telephone numbers and immediate persons to contact in the laboratory if an emergency arises. 11. 11 . Security requirements requirements for radioactive radioactive material material have been reviewed with the the worker.
The following safety safety documents and/or safety manuals manuals were reviewed by the worker. Note b a. Radiation Safety Manual b. Chemical Hygiene Plan c. Waste Disposal Guide d. Other (Please list). ___________________________________ ___________________________________ Sign up to vote on this title
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Worker Work er Co Cons nsen ent: t: I certi certify fy that that I have have been been provid provided ed with with and unders understan tand d the the infor infor indicated above. I understand that this this is a certification certification of principal investigator trainin trainin informed consent, and does not constitute a waiver of my rights. I understand that
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INSTRUCTIONS FOR PRINCIPAL INVESTIGATOR TRAINING
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1.
Indi Indivi vidu dual alss freq freque uent ntin ing g an are areaa wher wheree radi radioa oact ctiv ivee mate materi rial alss are are used used,, stor stored ed or or disposed should receive principal investigator training. This training may be documented with this checklist.
2.
Traini Training ng is funct function ion specif specific ic and site site specif specific, ic, meanin meaning g the the cont content ent and depth depth of training is related to the duties of the person and the scope of the hazards present in the work area.
3.
Expos Exposur uree lim limit itss mus mustt be be expl explai ained ned to worker workers. s. For perso persons ns who are not certi certifi fied ed radiation workers, the exposure limits are General Public, or 100 mrem per year. For radiation workers, the limits are the occupational limits set forth in the 10 CFR 20 laws, or 5 rem per year TEDE (whole body), 50 rem per year to an organ, 15 rem per year to the lens of the eye, 50 rem per year for the skin of the whole body and/or extremities. Radiation workers must have received introductory safety training at the ORCBS, and must attend annual refreshers for radiation and hazardous waste.
4.
Copi Co pies es of the the tra train inin ing g rec recor ords ds may may be be kep keptt in in the the safe safety ty note notebo book ok..
5.
Secur Securit ity y and and cont contro roll of radio radioact activ ivee mater materia ials ls must must be provi provided ded at all all times times,, eith either er with persons present or locking or securing to prevent tampering or unauthorized use or removal. Persons who are not radiation workers may provide this control if they are appropriately trained by the PI and/or the ORCBS radiation safety training class.
6.
This This docu docume ment nt serv serves es as info inform rmed ed cons consen entt of of the the work worker er..
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Pointers for Handling Radioactive Waste
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1.
Read and under understa stand nd the the Michig Michigan an State State Univ Univers ersity ity Waste Waste Disp Disposa osall Guide Guide.. This This do should be located in your laboratory.
2.
If you you need need an empty empty contain container, er, but but have have no waste waste to be picked picked up, photo photocopy copy the f the Waste Disposal Disposal Guide. Fax or mail it to to the ORCBS stating stating that this is a cont request, and ask for the number of containers you need.
3.
As soon soon as you recei receive ve the the contain containers ers in in your lab, lab, fill fill out the the bottom bottom part part of of the back back s the waste tag. This information identifies identifies your laboratory, including room number, bui name, phone number, principal investigator and the signature of a radiation worker.
4.
A separat separatee contain container er must must be used used for for each each isoto isotope pe you you will will be using using,, with with the excep excep 3H & 14C; these isotopes can be mixed in the same container.
5.
You must must separ separate ate the soli solids ds and and the the liqui liquids. ds. Under Under no no circu circums mstan tance ce shou should ld liqu liqu placed in the solid waste or solid material placed in the liquid waste.
6.
You must must have second secondary ary contai containment nment for your liquid liquid radioa radioactiv ctivee waste waste contai container( ner(s), s), of a leak or there is some spillage when filling the container, or rupture of the container.
7.
Record Record the the isoto isotope, pe, activ activity ity,, date date and initi initials als ever every y time time materia materiall is added added to the the container(s). Each pair of gloves or pipette tip need not be manifested, but there should entry for each experiment or day that material is added.
8.
Be sure sure to list list the chemical chemical components components of the the liqui liquid d waste waste on the the back back of of the the waste waste the chemical name followed by the percent "by volume" or other units to quantify chemical. This helps the ORCBS determine how to route the waste.
9.
Fill Fill the the liquid liquid containe container(s r(s)) only only to to 3 inche inchess from from the the top. top. Overfil Overfilling ling the conta container iner present a hazard to the lab as well as the ORCBS ORCBS personnel. When the container is or ma photocopy and fill out the form on Page 14 of the Waste Disposal Guide and fax Sign up to vote on this title the ORCBS requesting a pickup. Please complete the form for each solid, liquid, anim Useful for activity Not vial waste you want picked up, and put the isotope and eachuseful container.
10. 10 . Mixed waste waste (waste (waste that is is both radioactive radioactive and chemicall chemically y hazardous), hazardous), must be dispos dispos
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Pregnant Radiation Worker Policy at MSU
On January 1, 1994, the new Title 10, Code of Federal Regulations, Regulations, Part 20 law went into eff the United States. Many changes were made in these laws which directly affect use radioactive materials and radiation at Michigan State University. This document describe changes and requirements for pregnant radiation workers, and things that Michigan University and the worker must do to assure that exposures or risks are maintained at or belo legal requirements. Requirements are:
1 . The limit limit for radiati radiation on exposure exposure for a declared declared pregnant pregnant radiati radiation on work 500 mrem for the entire gestation period. 2 . There is now now a separate separate limit limit for the the fetus of 500 mrem mrem for the e gestation. 3 . Exposures Exposures to the the fetus fetus must be be uniform, uniform, and will will be maintain maintained ed at or b 50 mrem per month. 4 . Declaration Declaration of pregnancy pregnancy is optional. optional. Pregnant radiation radiation workers declare their pregnancy in writing to the Radiation Safety Officer for fetal and prenatal limits to to take effect. If no written declaration is the limits remain at the occupational limit (5 rem per year). 5 . If exposures exposures have occurred occurred between between the the time of conception conception and declaration date, the exposures will be subtracted from the perm exposure limits, and the balance will be prorated over the remai months. 6 . A meeting meeting will be be scheduled scheduled with with the pregnant pregnant worker worker and a health health ph staff member to review the previous exposures, discuss any partic concerns and review any special precautions or particular concern radiation uses. 7 . Pregnant radiati radiation on workers will be supplie supplied d with two two radiation radiation dosim one for the mother (whole body), and one for the fetus (abdomen). (abdomen). badges will be exchanged monthly in order to assure that an expo spikes do not occur, and to document that exposures do not exceed th Sign up to vote on this title mrem/month cap. useful Usefulseparate Notly 8 . Exposure Exposure records for for the fetus fetus will be be tracked separately from the the mo This eliminates confusion and assures that the accumulated dose wraps the next year if the pregnancy carries into that year.
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Properties of Some Commonly Used Beta Emitters Sheet Music
3H
14 C
Half Life
1 2. 3 y
5 73 0 y
16 3 d
1 4. 3 d
Max beta energy (MeV)
0.0186
0.156
0 .2 5 7
1 . 71
0 .006
0.049
0.0 77
0.70
0 .0 0 05 2
0 .0 2 9
0. 06
0.8
Property
Average beta energy (MeV) Range (cm) in unit density material
45 C a
3 2P
90
HVL (cm), unit density absorber
---
0 .0 0 2 2
0 . 00 4 8
0 . 10
Dose rate from 100 beta
---
56
33
11
---
0 . 11
0. 37
0. 9 5
---
1,400
4,00 0
9,20 0
2
particles/cm2sec-1 (mrad/hr)c Fraction transmitted through dead layer of skin (0.007 cm) Dose rate (mrad/hr) to basal cellsd of
17
epidermis per mCi/cm2 a. b. c. d. e.
From the 90Y decay product. 90Sr emits 0.55 MeV (max) beta. 90 Sr (0.196) + 90 Y (0.93). The dose dose rate rate for 100 b parti particl cles/ es/cm cm2-sec is for a parallel beam. The dose rate to basal cells cells of the the epidermis epidermis is from from beta particles emitted in all directions equally from from contamination on the surface surface of the skin. Basal cells are considered to be 0.007 cm below the surface. The dose dose rate rate to to basal basal cells cells of the the epiderm epidermis is listed listed for 90Sr includes the 90Y contribution. Data for half-li and maximum and average beta energies taken from MIRD, 1975.
(J. Shapiro, Radiation Protection--A Guide for Scientists and Physicians )
Tissue Dose Rate (rads/hr) at Various Distances Around a 1 uCi Particle o Various Beta Emitters (Range in Tissue - 10 mm.) Sign up to1vote on this title
um
mm
14 C
90 S r
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32 P
90 Y
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RADIOLOGICAL UNITS Sheet Music
Unit Curie
Symbol Ci
Becquerel Roentgen
Bq R
Brief Description 3.7 x 1010 disintegrations per second (2.22 x 1012 DPM) 1 disintegration per second 2.58 x 10-4 C/kg. (photons in air)
Rad
rad
0.01 J/kg (100 ergs/g)
Gray
Gy
1 J/kg.
Dose Equivalent
H
Quality Factor
Q
Rem
rem
Sievert
Sv
Dose x Q x any other modifying factors Biological effectiveness related to type of radiation Rad dose x Q x any other modifying factors Gy x Q x any other modifying factors
Use Special unit of activity
SI unit of activity Special unit of exposu applies only to gamma x radiation Special dose unit; app any radiation SI unit of dose (Equa rads) Radiation protection Radiation protection
Special unit of human d equivalent SI unit of human d equivalent (Equals rem)
RELATIONSHIP BETWEEN SPECIAL AND SI UNITS Activity: Exposure: Dose: Dose Equivalent: KeV: MeV:
1 Ci = 3.7 x 1010 Bq = 2.22 x 1012 DPM 1 R = 2.58 x 10-4 C/kg. The special unit for exposure is the Roentgen. There is no SI unit for exposure; it is simply expressed in C/kg. 100 rads = 1 Gy Sign up to vote on this title 100 rems = 1 Sv Kilo (1000) electron volts Useful Not useful Mega (1,000,000) electron volts 1 MeV = 1000 keV
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RADIOISOTOPES COMMON AT MSU Sheet Music
Iso to p e
Half-Life
C o u n ti n g M e t h o d
Typical Efficiency*
Energy, MeV (b)
Energ MeV (
3H
12.35 years
L.S.C.
50 %
0. 0 1 86
No
14C
5730 years
L.S.C., Pancake
75%, 5%
0.157
No
22Na
2.6 years
2:2 Gamma, 1:1 Gamma
30%, 15%
0.546
0 .511
32P
14.3 days
Pancake
50%
1 .7 1
No
33P
25.3 days
Pancake
15%
0.248
No
35S
87 . 5 d a y s
L . S . C . , Pa n c a k e
7 5 %, 5 %
0.167
No
36Cl
3.0 E5 years
Pancake
30%
0.709
No
40K
1.28 E9 years
Pancake
50%
1 .3 3
1.4
45Ca
163 days
Pancake
15%
0.258
0.0
(x-ray 46Sc
84 days
51Cr
Pancake, 1:1 Gamma
20%, 15%
0.357
27.7 days
L.E.G.
20%
None
0.3
55Fe
2.7 years
Pancake
15%
0.232
No
63Ni
100 years
L.S.C.
50 %
0. 0 6 69
No
65
243.8 days
1:1 Gamma, Pancake
15%, 15%
0.325
1.1
85Sr
64.8 days
L . E . G.
15 %
None
86Rb
18.6 days
Pancake, 1:1 Gamma
50%, 20%
1.775
Zn
1 .12,
0.5 1.0771 (9%
abundan 111In
2. 8 d a y s
L.E.G.
20up %to vote on this Notitle ne Sign
125I
60 days
L.E.G.
Useful
50%
Not useful None
0.2
0.171 0.0
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Security and Storage of Radioisotopes Sheet Music
Security
It is required by U.S. Nuclear Regulatory Commission law that security of radioactive mat must be in place at all times. times. Violations of this this regulation are frequently frequently cited at institu institu utilizing radioactive materials, and place the license to use such materials in jeopardy. The Co Federal Regulations, Title 10, Part 20.1801 and 20.1802, Storage and Control of Lice Materials in Unrestricted Areas, reads: (a )
The licens licensee ee shall shall secure from unauthorized unauthorized removal or access access lice materials that are stored in controlled or unrestricted areas. (b ) The license licenseee shall contro controll and maintai maintain n constant constant surveil surveillance lance of of lice material that is in a controlled or unrestricted area and that is no storage.
This means that all locations where radioactive materials are present must be in constant attend by the trained user, or otherwise locked or secured to prevent unauthorized removal or tamper
Storage
Storage of radioactive materials shall be in secured or locked cabinets, refrigerators, freeze waste areas, unless attended by the licensee. Radioactive materials shall be stored in s containers in such a way as to prevent accidental spillage or breakage, and to prevent releas the air. If the nuclide requires shielding, it shall be stored in shielded containers in order to pr doses to personnel accessing the storage areas.
If the radioactive material has been stored in a freezer or ultra freezer, it is imperative tha material be thawed, opened and handled in a certified fume hood or biological safety ca Aerosols from stored radioactive materials may cause contamination of adjacent areas and dos personnel if not handled in the proper way after storage. Sign up to vote on this title
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All radioactive materials, whether in storage, waste or use, must be labeled with the radioa warning symbol, the words "Caution, Radioactive Materials", Materials", the isotope, the date and the am of radioactivity in DPM or microcuries.
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ORCBS RADIOISOTOPE LABORATORY SURVEY Sheet Music
Location Project Leader
Isotopes Used Contact Person
Date
CHECKLIST: (Items marked "No" require corrective action). Yes 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12.
No
NA
___ ___ ___ NRC "Notice To Employees" & "Licensing & Regulation Information" are po ___ ___ ___ Radioactive materials are under constant surveillance and immediate __ _ __ _ __ _ __ _ __ _ __ _ __ _ __ _ __ _ __ _
__ _ __ _ __ _ __ _ __ _ __ _ __ _ __ _ __ _ __ _
__ _ __ _ __ _ __ _ __ _ __ _ __ _ __ _ __ _ __ _
13. ___ ___ ___
licensee, or otherwise secured to prevent tampering or unauthorized remova Radiation users are adequately trained for functions performed. Surveyed areas are free of radioactive contamination. Laboratory radiation survey equipment is functional and used correctly. Laboratory radiation surveys are accurate and frequency is appropriate. Food & other consumables are not present in radioisotope & chemical use/st Radioisotope work areas, storage areas and equipment are labeled adequat Radioisotope sources/stock solutions are labeled adequately. Radioisotope waste is manifested on both sides of the tag, 2 ° containment fo Radioisotope shielding is adequate (material, thickness, positioning). Dosimeters, if assigned, and protective equipment are used during r handling. Fumehoods are used properly (sash setting, uncluttered, rated for radioisoto
#: Not observed; no radioactive radioactive work at time of survey survey or no radiation workers present present in laborator Comments:
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RADIATION SURVEY MAP OF ROOM C32B ENGINEERING RE Sheet Music
B
H
S
S
S
GC S Scint. Counter
WA
B
R
KEY KE Y (B)=Bench, (H)=Hood, (S)=Sink, (R)=Refrigeration unit, (WA)=Waste container, (
)=Wipe sample
(------)=Meter survey area, (X)=Contamination area ( ≤100cm2 unless stated otherwise)
Survey Instrument Information Make:
Model:
Serial No:
(Rateme
Make:
Model:
Serial No:
(Rateme
Detection Sensitivity Information Nuclide
B.G. (CPM)
Eff.(%)
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Survey Results
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Transportation Instructions for Radioactive Material Sheet Music
Requirements for the transportation of radioactive material on campus and to other institutions comply with both the NRC and DOT regulations. Transporting may involve walking or dr radioactive material across across campus, or shipping off campus. The ORCBS must be notified b any transfers take place. This is to insure that proper procedures are followed and movem radioactive material is tracked. Any transfers of radioactive material material (possession transferred transferred one principal investigator to another) must to be pre-authorized by the ORCBS. Package Preparation
All packages used to transport radioactive material must be strong, tight containers that wi leak under normal transportation conditions (such as dropping, jarring or temperature extre If liquid is shipped, use at least twice the amount of absorbent needed to contain the entire vol in case the container should break or leak. If you are not sure sure whether the container you p use is adequate, contact the ORCBS. Transportation on Campus
Whenever radioactive material is transported from one building to another, the ORCBS mu notified of the following information: • • • • • • • • •
When the the material material will will need to to be moved moved The names of the person person sending and receiving receiving the material material (if (if different) different) The sending sending and and receiving receiving locations locations The nucli nuclide( de(s) s) being being moved moved The chemical chemical form of the isotope isotope The total total activity activity in mCi mCi Number Number of containe containers rs Phone numbers numbers of responsib responsible le persons persons Any speci special al condit condition ionss
Walking to another building Sign up(see to vote on this title Prepare to move your material using an appropriate container Package Preparation ab The package must have a radioactive warning label with theUseful isotope, activity in DPM, uCi o Not useful and date. Clearly identify identify the principal investigator investigator and one other contact in case of an accid loss of the package. The package must be tested for removable contamination before it leav place of origin and after it reaches it destination. Contact the ORCBS if any remo
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condition of the package must be checked and a leak test performed performed by the ORCBS. A rad worker must be present at the receiving rece iving location to take possession of the material at the arra time. Shipping Radioactive Material
When preparing to ship radioactive material, whether it is radioactive samples or a pie equipment being returned for repairs, the ORCBS must be informed in advance. Do not ex regulations must must be followed followed regardless to send shipments out immediately . Federal regulations quantity being sent.
Shipments can only be made to institutions that are licensed to possess radioactive material. shipping to another licensee, it is required that prior authorization be obtained from the Radi Safety Office at that location, preferably the Radiation Safety Officer. License information m on record or obtained before the shipment can be sent. To initiate this process, process, the person se the material must have the following information: • • • • • • • • •
The name of of the person person sending sending the the material material Facilit Facility y name and and addres addresss The name of the the person receivi receiving ng the material material The Radiation Radiation Safety Officer’s Officer’s (or (or other staff staff member) name name and phone number The nucli nuclide( de(s) s) being being sent sent The chemical chemical form form of each isotope isotope The total total activity activity in in mCi for each isotope isotope Number of containers containers in the shipment shipment Any speci special al condit conditions ions..
Radioactive material is sent from this university through the MSU Stores mail room. A ma return (MR) form must be filled out by the department and completed by MSU Purcha Purchasing will then assign an MR number to the the shipment. The Stores mail room will not the package without this number.
Prepare to ship your material using an appropriate container (see Package Preparation above) ORCBS will determine determine what package labeling is required. Do not seal the package, a condition of the package must be checked and a leak test performed by the ORCBS. Labels w placed on the package, if required. When the package and order, the OR Signpaperwork up to vote onare thisin title will transport the package to the MSU Stores mail room. room. Copies theNot shipping Useful of useful papers, ma return form, and any other paperwork will be made and maintained for review at the ORCBS.
Remember that shipments of radioactive material must be plan
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References and Other Resources SELECTED BIBLIOGRAPHY
(and additional sources of information)
Brodsky, A. 1978. CRC Handbook of Radiation Radiation Measurement Measurement and Protection. Protection. Boca Raton, FL: CRC Press Cember, H. 1996. Introduction to Health Physics. (3rd Edition) New York: McGraw-Hill. Cobb, Charles E., Jr., and Karen Kasmauki. 1989. Living With Radiation. National Geographic, 175: 402 Cohen, Bernard L. 1991. Radiation Standards Standards and Hazards. IEEE Transactions Transactions on Education, Education, 34: 260-265. 260-265. Henry, Hugh. 1969. Fundamentals of Radiation Protection. New York: York: Wiley-Interscience.
Martin, Alan, and Samuel A. Harbison. 1986. An Introduction to Radiation Radiation Protection. New York: Chapm Hall.
Miller, Kenneth L. 1992. CRC Handbook of Management of Radiation Protection Programs. Boca Rato CRC Press, Inc. Moeller, Dade. 1992. Environmental Health. Cambridge, MA: Harvard University Press. Shleien, Bernard, ed. 1992. The Health Physics and Radiological Health Handbook. Silver Spring, MD: Inc. Shapiro, Jacob. 1990. Radiation Protection. Cambridge, MA: Harvard University Press.
Yalow, Rosalyn S. 1994. Concerns with Low-level Ionizing Radiation. Mayo Clinic Proceedings, 69: 436-4 Fundamentals of Radiological Protection. 1993. Radiation Safety Associates Publications, 19 Pendleton P.O. Box 19, Hebron, CT 06248. (203) 228-0824
Radiological Health Handbook. Handbook. 1970. Compiled and edited by the Bureau of Radiological Radiological Health and The Tr Institute, Environmental Control Administration. Administration. Washington, D. C.: Government Printing Office. Sign up to vote on this title
Not useful Chart of the Nuclides. Nuclides. 14th edition. edition. Available as wall chart (50" (50" 29") or booklet (8 (8 1/2" x 11") from xUseful Nuclear Energy, General Electric Company, Nuclear Energy Operations, 175 Curtner Ave, M/C 397 Jose, CA 95125. Cost: approx. $12.
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The International Atomic Energy Agency issues many publications pertaining to the nuclear science field, incl the proceedings of symposia, a Safety Series covering topics in radiation protection, a Technical Re Series, a Bibliographical Series, and a Review Series. A complete catalog of publications may be ob from the Publishing Section, International Atomic Energy Agency, Karnter Ring 11, P. O. Box 59 1011 Vienna, Austria. Publications may be ordered from UNIPUB, Inc., P. O. Box 433, New Yor 10016.
National Consensus Standards relating to radiation protection provide information and guidance, and are incorporated into the regulations of the Nuclear Regulatory Commission. The major national organi issuing such standards is the American National Standards Institute (ANSI), 1430 Broadway, New NY 10018.
The U. S. Nuclear Regulatory Commission issues guides that describe methods acceptable to the NRC sta implementing specific parts of the Commission's Commission's regulations. Request information from the U. S. N Regulatory Commission, Commission, Washington, Washington, D. C. 20555, Attention: Director, Office of Nuclear Regu Research.
Health Physics, the official journal of the Health Physics Society, is a valuable source of information in rad protection.
Health Physics Society Newsletter, a publication of the Health Physics Physics Society, 8000 Westpark Westpark Dr., St McLean, VA 22102. Radiation Protection Management: The Journal of Applied Health Physics. RSA Publications, 19 Pendleton P. O. Box 19, Hebron, CT 06248.
OTHER REFERENCE RESOURCES Excellent resources are available on the computer internet. Several are listed below. ORCBS WWW Home Page: http://www.orcbs.msu.edu RADSAFE: A listserve for radiation radiation safety. To subscribe, send an email request request to: romulus.ehs.usuc.edu
SAFETY: A world wide listserve listserve for general general safety. To subscribe, send seSign nd email requ uvmvm.uvm.edu uvmvm.uvm .edu up to request voteest ontothis title
Useful Radiation and Health Physics Physics Home Page: http://www.umich.edu/~bbusby/ http://www.umich.edu/~bbusby/
Not useful
University of Michigan Michigan Radiation Safety Home Page: http://www.umich.edu/~oseh/rss.html
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Glossary
Sheet Music
Absorbed Dose the amount of energy imparted to matter by ionizing radiation per unit mass of irradiated irradiated material. of absorbed dose is the rad, which is 100 ergs/gram.
Absorption the phenomenon by which radiation imparts some or all of its energy to any material through which it p
Activation the process of making a material radioactive by bombardment with neutrons, protons, or other n radiation. Activity the number of nuclear disintegrations occurring in a given quantity of material per unit time.
Acute Exposure the absorption of a relatively large amount of radiation (or intake of radioactive material) over a short per time.
Acute Health Effects prompt radiation effects (those that would be observable within a short period of time) for which the se of the effect varies with the dose, and for which a practical threshold exists. Adult
an individual 18 or more years of age.
ALARA (acronym for As Low As Reasonably Achievable) making every reasonable effort to maintain exposu radiation as far below the dose limits as is practical consistent with the purpose for which the licensed ac is undertaken, taking into account the state of technology, the economics of improvements in relation to of technology, the economics of improvements in relation to benefits to the public health and safety other societal and socioeconomic considerations, and in relation to utilization of nuclear energy and lic materials in the public interest.
Alpha Particle charge a strongly ionizing particle emitted from the nucleus during radioactive having a mass and Sign up todecay vote on this title in magnitude to a helium nucleus, consisting of 2 protons and 2 neutrons with a double positive charge.
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Alpha Ray a stream of fast moving helium nuclei (alpha particles), a strongly ionizing and weakly penetrating radia
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Attenuation the process by which a beam of radiation is reduced in intensity when passing through some material the combination of absorption and scattering processes and leads to a decrease in flux density of the when projected through matter.
Background Radiation ionizing radiation arising from radioactive material other than the one directly under consider Background radiation due to cosmic rays and natural radioactivity is always present. There may a background radiation due to the presence of radioactive substances in other parts of the building, i building material itself, etc.
Becquerel the international (SI) the unit for radioactivity in which the number of disintegrations is equal to disintegration per second. A charged particle emitted from the nucleus of an atom during radioactive deca
Beta Particle charged particle emitted from the nucleus of an atom during radioactive decay. A negatively charge particle is identical to an electron. electron. A positively charged beta particle particle is called a positron. Beta Ray a stream of high speed electrons or positrons of nuclear origin more penetrating, but less ionizing than rays.
Bioassay the determination of kinds, quantities or concentrations, and, in some cases, the locations of radioa material in the human body, whether by direct measurement (in vivo counting) or by analysis and evalu of materials excreted or removed from the human body.
Body Burden the amount of radioactive material which if deposited in the total body will produce the maximum perm dose rate to the critical organ.
Bremsstrahlung electromagnetic electromagnetic (x-ray) radiation produced by the deposition of charged particles particles in matter. Secondary p radiation (x-ray) produced by the deceleration of charged particles through matter. Usually associated energetic beta emitters, e.g., 32P.
Calibration Sign up to vote on this title determination of variation from standard, or accuracy, of a measuring instrument to ascertain nece usefulent to assure p ofUseful Notinstrument correction factors. factors. The check or correction of the accuracy accuracy a measuring instrum operational characteristics.
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Committed Effective Dose Equivalent the sum of the products of the weighting factors applicable to each of the body organs or tissues th irradiated and the committed dose equivalent to these organs or tissues.
Contamination, Radioactive deposition of radioactive material in any place where it is not desired, and particularly in any place whe presence may be harmful. The harm caused may be a source of excessive exposure to personnel or the v of an experiment or a procedure.
Controlled Area an area, outside of a restricted area but inside the site boundary, access to which can be limited by the lic for any reason.
Cosmic Radiation penetrating ionizing radiation , both particulate particulate and electromagnetic, originating in space. Secondary c rays, formed by interactions in the earth's atmosphere, account for about 45 to 50 millirem annually.
Coulomb the meter-kilogram-second unit of electric charge, equal to the quantity of charge transferred in one second constant current of one ampere.
Count the external indication of a device designed to enumerate ionizing events. It may refer to a single de event or to the total registered in a given period of time. The term is often erroneously used to desig disintegration, ionizing event, or voltage pulse.
Critical Organ the organ or tissue, the irradiation of which will result in the greatest hazard to the health of the individ his descendants. Curie
the quantity of any radioactive material in which the number of disintegrations is 3.7 x 10 Abbreviated Ci.
10
per se s
Daughter Products isotopes that are formed by the radioactive decay of some other isotope. In the case of radium-22 example, there are ten successive daughter products, ending in the stable isotope lead-206.
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Decay, Radioactive useful Useful emission Notof disintegration of the nucleus of an unstable nuclide by the spontaneous charged particles a photons.
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Deep Dose Equivalent applies to external whole-body exposure and is the dose equivalent at a tissue depth of one centi (1000 mg/cm2).
Department of Transportation (DOT) a governmental agency responsible for promoting the safe transportation of hazardous materials by all m (land, air, water).
Depleted Uranium uranium having a percentage of uranium-235 smaller than the 0.7% found in natural uranium. uranium. It is ob from spent (used) fuel elements or as byproduct tails, or residues, from uranium isotope separation.
Derived Air Concentration (DAC) the concentration of a given radionuclide in air which, if breathed by the reference man for a working y 2,000 hours under conditions of light work (inhalation rate 1.2 cubic meters of air per hour), results intake of one ALI. Disintegration see decay, radioactive.
Dose or Radiation Dose a generic term that means absorbed dose, dose equivalent, effective dose equivalent, committed dose equiv committed effective dose equivalent, or total effective dose equivalent, as defined in other paragraphs o section. Dose Equivalent (H T ) the product of the absorbed dose in tissue, quality factor, and all other necessary modifying factors location of interest. The units of dose equivalent are the rem and the sievert (Sv). The ICRP defines the equivalent dose, which is sometimes used in other countries. Dose Rate the radiation dose delivered per unit of time. Measured, for example, in rem per hour.
Dosimeter a portable instrument for measuring and registering the total accumulated exposure to ionizing radiation dosimetry.)
Dosimetry Sign up to vote on this title the theory and application of the principles and techniques involved in the measurement and recordi ofUseful radiation doses. Its practical aspect is concerned with the use various types t ypesNot of useful radiation instrument which measurements are made (see film badge; thermoluminescent dosimeter; Geiger-Mueller counter).
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Electron negatively charged elementary particle which is a constituent of every neutral atom. Its unit of ne electricity equals 4.8 x 10 -19 coulombs. Its mass is 0.000549 atomic mass units.
Electron Capture a mode of radioactive decay involving the capture of an orbital electron by its nucleus. Capture fro particular electron shell is designated as "K-electron capture," "L-electron capture," etc. X-rays are produc
Electron Volt a unit of energy equivalent to the amount of energy gained by an electron in passing through a pot difference of 1 volt. Abbreviated eV. Radioisotopic energy energy is typically measured measured in MeV. (million volts). Erg Er g
the unit of energy or work in the centimeter-gram-second system; the work performed by a force acting distance of one centimeter so as to result in a one gram mass being accelerated at a rate of one centimete second each second.
Exposure (1) Being exposed to ionizing radiation or radioactive material. material. (2) a measure of the ionization produced by x or gamma radiation. It is the sum of the electrical charges on all ions of one sign produced in air all electrons liberated by photons in a volume element of air are completely stopped in air, divided b mass of air in the volume element. element. The special unit of exposure is the Roentgen. External Dose that portion of the dose equivalent received from radiation sources outside the body. Extremity hand, elbow, arm below the elbow, foot, knee, or leg below the knee.
Eye Dose Equivalent applies to the external exposure of the lens of the eye and is taken as the dose equivalent at a tissue dep 0.3 centimeter (300 mg/cm 2 ).
Film Badge a packet of photographic film used for the approximate measurement of radiation exposure for pers monitoring purposes. The badge may contain two or more films of differing sensitivity, and it may c filters which shield parts of the film from certain types of radiation. Sign up to vote on this title
Useful Not useful Fission the splitting of a nucleus into at least two other nuclei and the release of a relatively large amount of en Two or three neutrons are usually released during this type of transformation. transformation.
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Half-Life, Biological time required for the body to eliminate 50 percent of a dose of any substance by the regular proces elimination. This time is approximately the same for both stable isotopes and radionuclides of a part element.
Half-Life, Effective time required for a radioactive nuclide in a system to be diminished by 50 percent as a result of the com action of radioactive decay and biological elimination.
Effective half-life =
Biological half-life x Radioactive half-life Biological half-life + Radioactive half-life
Half-Life, Radioactive time required for a radioactive substance to lose 50 percent of its activity by decay. Each radionuclide unique half-life.
Half Value Layer the thickness of any specified material necessary to reduce the intensity of an x-ray or gamma ray be one-half its original value.
Health Physics a term in common use for that branch of radiological science dealing with the protection of personnel harmful effects of ionizing radiation. The science concerned with the recognition, evaluation and con health hazards from ionizing and non ionizing radiation.
High Radiation Area an area, accessible to individuals, in which radiation levels could result in an individual receiving a equivalent in excess of 0.1 rem (1 mSv) in one hour at thirty centimeters from the radiation source or any surface that the radiation penetrates.
Hot Spot the region in a radiation/contamination radiation/contamination area in which the level of radiation/contamination radiation/contamination is noticeably g than in neighboring regions in the area.
Individual Monitoring Devices devices designed to be worn by a single individual for the assessment of dose equivalent such as film ba thermoluminescent thermoluminescent dosimeters (TLDs), pocket ionization chambers, and personal air sampling devices.
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Intake Useful useful ingestion quantity of material introduced into the body by inhalation, or Not through the skin (absor puncture, etc.)
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Ionizing Radiation any radiation capable of displacing electrons from atoms or molecules, thereby producing ions. Exam alpha, beta, gamma, x-rays, neutrons and ultraviolet light. High doses of ionizing radiation may severe skin or tissue damage.
Ionization Chamber an instrument designed to measure the quantity of ionizing radiation in terms of the charge of elect associated with ions produced within a defined volume.
Ionizing Radiation alpha particles, beta particles, gamma rays, x-rays, neutrons, high speed electrons, high speed protons other particles or electromagnetic radiation capable of producing ions.
Isotopes nuclides having the same number of protons in their nuclei, and hence having the same atomic numbe differing in the number of neutrons, and therefore in the mass number. Almost identical chemical prop exist between isotopes of a particular element. Kinetic Energy the energy that a body possesses by virtue of its mass and velocity, the energy of motion. Joule
the meter-kilogram-second unit of work or energy, equal to the work done by a force of one Newton wh point of application moves through a distance of one meter in the direction of the force.
Labeled Compound a compound consisting, in part, of labeled molecules. By observations of radioactivity or is composition this compound or its fragments may be followed through physical, chemical or biolo processes. LD50/60 the dose of radiation expected to cause death within 60 days to 50 percent of those exposed.
Licensed Material source material, special nuclear material, or byproduct material received, possessed, used, transferr disposed of under a general or specific license issued by the Nuclear Regulatory Commission. Licensee the holder of the license.
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Useful
Not useful
Limits the permissible upper bounds of radiation exposures, contamination or releases.
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Minor an individual less than 18 years of age, as pertains to radiation exposure limits, works with radioa materials (not a member of the general public).
Molecule a group of atoms held together by chemical forces. A molecule is the smallest smallest unit of a compound th exist by itself and retain all its chemical properties.
Monitoring the measurement of radiation levels, concentrations, surface area concentrations or quantities of radioa material and the use of the results of these measurements to evaluate potential exposures and doses.
Natural Radiation ionizing radiation, not from manmade sources, arising from radioactive material other than the one dir under consideration. Natural radiation due to cosmic rays, soil, natural radiation in the human body and sources of natural radioactivity are always present. The levels of the natural radiation vary with loc weather patterns and time to some degree.
Neutron elementary particle with a mass approximately approximately the same as that of a hydrogen atom and electrically neut has a half-life in minutes and decays in a free state into a proton and an electron.
Non-Removable Contamination contamination adhering to the surface of structures, areas, objects or personnel and will not readily be p up or wiped up by physical or mechanical means during the course of a survey or during decontamin efforts.
NARM any naturally occurring or accelerator produced radioactive materials. It does not include byproduct, sour special nuclear material.
Neutron an uncharged elementary particle with a mass slightly greater than that of the proton, and found in the nu of every atom heavier than hydrogen. NORM naturally occurring radioactive materials.
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Nuclear Regulatory Commission (NRC) Not useful Usefuland an independent federal regulatory agency responsible for licensing inspecting nuclear power p universities and other facilities using radioactive materials.
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Occupational Dose the dose received by an individual in the course of employment in which the individual's assigned involve exposure to radiation and to radioactive material from licensed and unlicensed sources of radi whether in the possession of the licensee or other person. Occupational dose does not include dose rec from background radiation, as a patient from medical practices, from voluntary participation in me research programs, or as a member of the general public.
Particle Accelerator any machine capable of accelerating electrons, protons, deuterons, or other charged particles in a vacuu of discharging the resultant particulate or other radiation into a medium at energies usually in excess MeV. The National Superconducting Superconducting Cyclotron Laboratory is a particle accelerator. accelerator.
Photon a quantum (or packet) of energy emitted in the form of electromagnetic radiation. Gamma rays and x-ra examples of photons. Pig
a container (usually lead or plastic) used to ship or store radioactive materials. The thick walls prote person handling the container from radiation. Large containers are commonly called casks. Pocket Dosimeter a small ionization detection instrument that indicates radiation exposure directly. An auxiliary charging is usually necessary. Positron particle equal in mass, but opposite in charge, to the electron; a positive charge.
Principal Investigator (P.I.) a faculty member, assistant professor or higher (no visiting faculty), appointed by the licensee, who has approved through the Radiation Safety Committee for the purchase and use of radioactive materials.
Protective Barriers barriers of radiation absorbing material, such as lead, concrete, plaster and plastic, that are used to re radiation exposure. Proton an elementary nuclear particle with a positive electric charge located in the nucleus of an atom.
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Public Dose Usefuland Not useful material the dose received by a member of the public from exposure to radiation to radioactive material releas a licensee, or to another source of radiation. It does not include occupational dose or doses received background radiation, as a patient from medical practices, or from voluntary participation in medical res
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Radiation Worker an individual who uses radioactive materials materials under the licensees control. control. Individuals must be trained and passed a radiation safety examination prior to beginning work with radioactive materials. Radiography the making of shadow images on photographic film by the action of ionizing radiation.
Radioisotope a nuclide with an unstable ratio of neutrons to protons placing the nucleus in a state of stress. In an a to reorganize to a more stable state, it may undergo various types of rearrangement that involve the rele radiation.
Radiology that branch of medicine dealing with the diagnostic and therapeutic applications of radiant energy, includ rays and radioisotopes. Radionuclide a radioactive isotope of an element.
Radiosensitivity the relative susceptibility of cells, tissues, organs, organisms, or other substances to the injurious act radiation.
Radiotoxicity term referring to the potential of an isotope to cause damage to living tissue by absorption of energy fro disintegration of the radioactive material introduced into the body.
Reference Man a hypothetical aggregation of human physical and physiological characteristics arrived at by interna consensus. These characteristics may be used by researchers and public health workers to standardize res experiments and to relate biological insult to a common base.
Relative Biological Effectiveness for a particular living organism or part of an organism, the ratio of the absorbed dose of a reference rad that produces a specified biological effect to the absorbed dose of the radiation of interest that produc same biological effect. Rem
Sign up to vote on this title the special unit of dose equivalent. The dose equivalent in rems is numerically numerically equal to the absorbed d Useful useful factors. Not rads multiplied by the quality factor, distribution factor, and any other necessary modifying
Removable
Contamination
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Scintillation Counter a counter in which light flashes produced in a scintillator by ionizing radiation are converted into elec pulses by a photomultiplier tube.
Sealed Source radioactive material that is permanently permanently bonded or fixed in a capsule or matrix designed to prevent releas dispersal of the radioactive material under the most severe conditions which are likely to be encounte normal use and handling. Shallow Dose Equivalent applies to the external exposure of the skin or an extremity and is taken as the dose equivalent at a depth of 0.007 centimeter (7 mg/cm 2 ) averaged over an area of one square centimeter.
Shielding Material any material which is used to absorb radiation and thus effectively reduce the intensity of radiation, a some cases eliminate it. it. Lead, concrete, aluminum, water and plastic plastic are examples of commonly shielding material.
Sievert The international unit (SI) of dose equivalent (DE, human exposure unit), which is equal to 100 rem obtained by multiplying the number of grays by the quality factor, distribution factor, and any other nece modifying factors.
Site Boundary that line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee.
Somatic Effects of Radiation effects of radiation limited to the exposed individual, as distinguished from genetic effects, which may affect subsequent unexposed generations. Source Material 1. uranium uranium or thorium thorium in any combinat combination ion of uranium uranium and thorium thorium in any physica physicall or chemical chemical form; 2. ores that that contain, contain, by weight, weight, one-twentiet one-twentieth h of 1 percent percent (0.05%), (0.05%), or more, more, of uranium, uranium, thorium, thorium, combination of uranium and thorium. thorium. Source material does not include special special nuclear material.
Special Nuclear Material 1. plutonium plutonium,, uranium-23 uranium-233, 3, uranium uranium enriched enriched in the the isotope isotope 233 or in the the isotope isotope 235, and an but do material that the Nuclear Regulatory Commission determines material, Signto upbetospecial vote onnuclear this title include source material; or Useful usefulmaterial. Not 2. any material material artificiall artificially y enriched enriched by any of the foregoing but does not include inclu de source Specific
Activity
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Terrestrial Radiation the portion of the natural radiation (background) that is emitted by naturally occurring radioactive mater the earth. Thermoluminescent Dosimeter (TLD) crystalline materials materials that emit light if they are heated after being they have been exposed to radiation.
Total Effective Dose Equivalent (TEDE) the sum of the deep dose equivalent (for external exposures) and the committed effective dose equivalen internal exposures).
Tracer, Isotopic the isotope or non natural mixture of isotopes of an element which may be incorporated into a sam make possible observation of the course of that element, alone or in combination, through a chem biological, or physical process. process. The observations may be made by measurement measurement of radioactivit isotopic abundance.
Tritium a radioactive isotope of hydrogen (one proton, two neutron). Because it is chemically identical to n hydrogen, tritium can easily be taken into the body by any ingestion or inhalation path. Decays b emission. Its radioactive half-life is about 12.5 years. Unrestricted Area an area, access to which is neither limited nor controlled by the licensee. Unstable Isotope a radioisotope. Uptake quantity of material taken up into the extracellular extracellular fluids. It is usually expressed expressed as a fraction deposition in the organ from which uptake occurs.
Very High Radiation Area an area accessible to individuals, in which radiation levels could result in an individual receiving an abs dose in excess of 500 rads (5 grays) in one hour at one meter from a radiation source or from any surfac the radiation penetrates.
Weighting Factor (W T ) Sign up to vote on this title for an organ or tissue (T) is the proportion of the risk of stochastic effects resulting from irradiation o Useful Not usefuluniformly. organ or tissue to the total risk of stochastic effects when the whole body is irradiated uniformly. Pres the organ dose weighting defined by the NRC and the ICRP differ.
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