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There are no life threatening levels of radioactive materials
on the Susquehanna University campus. Nevertheless, it is the
policy of the University to maintain exposure to radioactivity
at levels
AS LOW AS REASONABLY ACHIEVABLE (ALARA).

 

 

 

 


EMERGENCY PROCEDURES

1. Call the Radiation Safety Officer. Dr. David S. Richard. Office phone 4206. Home phone 743 0232.

2. If an incident involving radioactivity presents other hazard potential such as fire or fume accumulation, also call Public safety (Ext. 4444).

3. If the emergency appears life threatening, also call Snyder County Emergency (911 or 837- 1131) and request and ambulance.

4. Remain on the scene to render assistance.

5. In the case of any incident involving radioactive material, call the Radiation Safety Officer (RSO).

Further safety and emergency instructions may be found in chapter 6

 

 

 

 

RADIATION SAFETY CALL LIST

Dr. David S. Richard Radiation Safety Officer Office phone 4206
Assistant Professor of Biology Home phone 743-0232

Dr. Jack Holt Biology Dept. Chair Office Phone 4205
Home phone 374-5324

Dr. Robert Nylund Chemistry Dept. Chair Office Phone 4223
Home Phone 374-8627

Dr. Katherine Miller Assistant Professor of Biochemistry Office Phone 4222

Dr. Tom Peeler Assistant Professor of Biology Office phone 4381 Home phone 374-8471

Dr. Tammy Tobin-Janzen Assistant Professor of Biology Office phone 4067
Home phone 966-0918

Public Safety 4444


Links within Document.

INTRODUCTION

ADMINISTRATION/ORGANIZATION

RESPONSIBILITIES

TRAINING

RADIONUCLIDE PROCUREMENT AND CONTROL

EMERGENCIES

SPECIFIC PROCEDURES FOR SPILLS

RADIOISOTOPE LABORATORY SAFETY RULES

GLOSSARY OF COMMON TERMS

APPENDIX

Measures to correct equipment deficiencies.

 


CHAPTER ONE
INTRODUCTION

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Ionizing radiation emitted from radioactive material is used at Susquehanna University for teaching and research purposes. Its use is not without some risk, however small, to the user, to other individuals, and the environs. The major objective of the Susquehanna University radiation safety program is to ensure the risk remains small by maintaining personnel exposures as low as reasonably achievable (ALARA). A second objective is the achievement of full compliance with state and federal laws and regulations governing the use of radioactive materials.

All personnel involved in the radiation safety program are invited to provide their recommendations for improving the program. The continued success of the program will be dependent not only upon maintaining exposures as low as reasonably achievable (ALARA) and complying with the rules and regulations, but also on our ability to adapt the program to changing research methods.

This manual is designed to inform Susquehanna University personnel of the basic requirements for the use of radiation generating devices and radioactive material within the Susquehanna University radiation safety program. More specific instructions for use, procurement, control, and disposal may be obtained from the Susquehanna University Radiation Safety Officer, Dr. David S. Richard (ext.4206).

Mankind has always been exposed to radiation. The source of this radiation includes cosmic rays, terrestrial radiation and radioactive atoms that are part of the make-up of the human body. In Central Pennsylvania this background radiation level is approximately 300 mrem per year.

The discovery of x-rays in 1895, the subsequent discovery of naturally occurring radioisotopes and the invention of accelerators, nuclear reactors and atomic weapons increased the sources of potential exposure. These various sources of ionizing radiation provide numerous benefits to modern man but are not without associated risks. Not only does radiation exposure present a risk to the exposed individual but it may also present a risk to his future offspring as well. The risks associated with high levels of radiation exposure are obvious, whereas the risks from low levels are uncertain and have led to much speculation and controversy. Since it is radiation exposure at any level may present a risk, it is advisable that exposures be kept as low as reasonably achievable (ALARA). Various agencies have developed recommended guidelines dealing with the use of and exposure to ionizing radiation. Among these are the National Council on Radiation Protection and Measurements (NCRP), the International Committee on Radiological Protection (ICRP), the International Commission of Radiation Units and Measurements (ICRU), the International Atomic Energy Agency (IAEA) and the Center for Devices and Radiological Health (CDRH). The United States Nuclear Regulatory Commission (NRC) and the Commonwealth of Pennsylvania's Bureau of Radiation Protection (BRP) have developed regulations pertaining to the usage of ionizing radiation.

Before we, as a university could obtain licenses to possess and use radiation sources, we had to develop safety guidelines and provide assurance that we would comply with these guidelines, the recommendations of the various radiation safety organizations and the regulations of the NRC and the BRP. Since Pennsylvania is not an "Agreement State", and since we do not possess any radiation generating machinery such as accelerators or X-ray machines, Susquehanna University are not regulated by the Commonwealth of Pennsylvania but by the NRC under a license that covers reactor byproduct material.

The rules and procedures outlined in this manual have been developed to protect students, visitors, employees and the Susquehanna University facility from unnecessary and potentially harmful radiation exposure and costly decontamination measures.


CHAPTER TWO
ADMINISTRATION/ORGANIZATION

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Susquehanna University President

Vice President for Academic Affairs

Radiation Safety Officer

Investigators

 

 

 

 

 


This chart shows the organization of those responsible for directing the radiation safety program at Susquehanna University. The Susquehanna University radiation safety program is governed by external regulatory requirements (i.e. state and federal licenses) as well as by Susquehanna University policy. While the radiation safety program must meet the conditions specified by the licenses, Susquehanna University has the responsibility for designing, implementing and maintaining the program.

LICENSE

 

 

 

 

Susquehanna University currently holds one Federal materials license: #37-15672-01
Amendment # 08
Expiration date 08-31-04

The license is kept by the RSO and is available for inspection.

 

 

 

 

 


CHAPTER THREE

RESPONSIBILITIES

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RADIATION SAFETY OFFICER

The Radiation Safety Officer is responsible for:
1. radiation monitoring and evaluation:

a. coordinating an evaluation of each proposed use of radioactive material;

b. directing the routine monitoring or special surveys of all areas where radioactive material is used;

c. conducting periodic reviews and surveys of work areas to ensure license conditions are not violated;

d. ensuring radiation detection instrumentation is calibrated by a licensed vendor or by Nuclear Regulatory Commission (NRC) approved procedures.

2. supervising the transfer and storage of radioactive material:

a. supervising shipments of radioactive material leaving Susquehanna University;

b. supervising and coordinating radioactive waste disposal;

c. overseeing storage of all radioactive materials (including wastes);


3. maintaining appropriate records:

a. keeping a total campus inventory of radionuclides, (ensuring only the authorized quantities and forms are used);

b. conducting a physical inventory every six-months;

c. supervising the distribution and processing of personnel monitoring devices if required;

d. collecting and evaluating bioassays if required;

e. maintaining personnel exposure and bioassay records if required;

f. maintaining records of surveys, radiation monitoring disposal, receipts, and transfers as required by the licenses;

4. conducting programs to train users of radioactive material;


5. responding to emergencies involving radioactive materials;

6. advising on all aspects of radiation safety to personnel at all levels.



The RSO has the authority to:
1. approve or reject any request to use radiation;
2. establish training and experience criteria in consultation with Susquehanna University faculty and administration;

3. withdraw approval for use of any radiation source.

PRINCIPAL INVESTIGATORS

Principal investigators are personally responsible for:

1. training research staff and students as to lab protocol;

2. submitting applications to the RSO prior to the use of radionuclides or radiation generating equipment;

3. notifying the RSO in writing of personnel terminations;

4. ensuring that lab workers have received Susquehanna University radiation safety training and proper dosimetry (if required) before beginning work in the lab.

5. implementing corrective actions to prevent recurrence of radiological incidents.


Principal investigators must ensure that the following are accomplished, but may delegate the implementation:

1. performing lab work in accordance with Susquehanna University radiation safety program requirements;

2. notifying the Radiation Safety Officer of significant radiological incidents (such as spills or personnel contamination);

3. maintaining an accurate and thorough radioactive material inventory for the lab;

4. notifying the Radiation Safety Officer of all transfers of radioactive material or radiation generating devices to or from another lab or licensee;

5. notifying the Radiation Safety Officer of any changes in the methods used for handling radioactive material, for which authorization has been approved by the Radiation Safety Officer.

RADIONUCLIDE USERS

 

 

 

 

Radionuclide users are responsible for knowing and following general safety instructions while working with radioactive materials. (See Appendix II: Susquehanna University Radiation Laboratory Safety Rules.) in addition, they are responsible for:

1. keeping badges (if required) in the designated storage area when not in use;

2. recording radionuclide use and disposal in an inventory log;

3. estimating activity of radioactive waste, packaging it in a designated container, and labeling it appropriately;

4. notifying the Radiation Safety Officer of spills, loss of radioactive materials, or personnel contamination;

5. preventing unauthorized personnel from entering the lab;

6. ensuring doors are locked or material is under constant surveillance if the laboratory can not be secured;

7. ensuring radioactive material removal is conducted only by authorized (by the RSO) Susquehanna University staff.


CHAPTER FOUR
TRAINING

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GENERAL REQUIREMENTS

Training is mandatory for all personnel entering radiologically restricted areas (radionuclide users, radiation generating device users, and ancillary personnel) and for Principal investigators. Training review is conducted annually. Please see the Radiation Workers Training form

RADIONUCLIDE USERS

Radionuclide users and their P.I.'s receive training in:
1. radioactive material hazards;
2. exposure modes;
3. contamination and radiation controls;
4. radioactive material/waste controls;
5. personnel monitoring devices (if required);
6. rights and responsibilities;
7. emergency actions.

ANCILLARY PERSONNEL

Ancillary personnel receive training in:
1. types of radiological posting, labels, and tags;
2. potential radioactive material hazards;
3. rights and responsibilities;
4. emergency actions.

EMERGENCY PERSONNEL

Emergency personnel receive training in:
1. radioactive material hazards;
2. types of radiological posting, labels, and tags;
3. exposure modes;
4. contamination and radiation controls;
5. emergency actions.

EXEMPTIONS

Users are exempt from training if:

1. they have two years previous experience working with radioactive material/radiation generating devices OR previous radiation safety training at another institution (documented in writing);

2. their previous experience is similar or applicable to current work as determined by the RSO;

Ancillary personnel are exempt from training if:

1. they are escorted by a trained user while in a restricted area;

2. no radioactive material is in use in the restricted area;

3. they will not be exposed to levels of radiation detectable by personnel monitoring devices while in the area.

 

 

 

 

DOCUMENTATION

Training forms must be completed for all radiation workers (see Form Radiation Worker Training Form in appendix). This includes all students. Principal Investigators must file a curriculum vitae with the RSO outlining their experience working with isotopes (itemize isotopes and procedures) and any radiological training courses that they have attended.


CHAPTER FIVE

RADIONUCLIDE PROCUREMENT AND CONTROL

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In order to carefully monitor all radioactive materials, Susquehanna University must follow strict guidelines concerning the receipt, distribution, control, and inventory of radioactive material.

 

OBTAINING RADIOACTIVE MATERIALS

 

 

 

 

1. The user must discuss with the Radiation Safety Officer the nature and amount of radioactive materials to be purchased.

2. The Radiation Safety Officer will evaluate the request in the context of the license. The requested amount must be within the authorization limits. If approval is granted, the Radiation Safety Officer will inform the user that the purchase may be made. This procedure should be followed even in the case of exempt quantities of isotopes.

3. The user will arrange for the purchase, asking the vendor to send the material
C/O Dr. David S. Richard/ user name (Fisher Hall Room 217)

RECEIVING THE RADIOACTIVE MATERIAL

 

 

 

 

1. The requested radioactive material will arrive at the office of the RSO, Dr. David S. Richard (Fisher Hall Room 217). If alternate locations are desired, the Radiation Safety Officer must approve and specify on the purchase order.

2. The RSO will perform contamination and radiation surveys of the exterior surface of the package the package interior and radionuclide container.

3. If the radioactive material is within the accepted limits (less than 200dpm removable contamination) the user will be notified to pick up the package.

4. Each radionuclide will be issued with an inventory control number (XX-XXX) and a
radiation inventory sheet

MAINTAINING AN INVENTORY

1. An inventory record includes information concerning the storage, disposal, transfer, and present usage of the radioactive material.

2. the form
Radiation Inventory Sheet is used to record inventory information.

3. The form, along with instructions of its use, is available from the RSO.

4. The individual laboratory is responsible for logging in received or transferred radioactive material and logging out material disposed as waste.

TRANSFERRING RADIOACTIVE MATERIAL TO SUSQUEHANNA UNIVERSITY

1. To transfer radioactive material from another licensee to Susquehanna University, you must have the approval of the RSO.

2. Susquehanna University's license must allow for the possession and use of the radioactive material transferred.

3. Contact the Radiation Safety Officer to arrange the details of the transfer.

TRANSFERRING RADIOACTIVE MATERIAL FROM SUSQUEHANNA UNIVERSITY

1. To transfer radioactive material from Susquehanna University to another licensee, the Radiation Safety Officer's approval is required.

2. The RSO will determine if the licensee can use and possess the amount and type of radioactive material.

3. The RSO will ensure that the material is properly packaged and labeled, and that the shipping papers are completed.

4. Contact the Radiation Safety Officer to arrange the details of the transfer.

DISPOSING OF RADIOACTIVE MATERIAL

WASTE CONTROL

1. Only the RSO and authorized (by the RSO) personnel are authorized to remove and dispose of radioactive material from authorized facilities. Waste disposal will be conducted according to NRC Regulations Part 20, Subpart K.

2. The users will ensure that the short (<120 days) half lived material is separated from long (>120 days) half lived materials. It is preferable, though not mandated by the conditions of the NRC license, that
32P waste and 35S waste streams remain separate.

3. Long physical half-life contaminated (tritium) glass waste and plastic will be separated from paper waste. The glass and plastic will be soaked in water to remove contamination. The water will be tested (by liquid scintillation counting) for the level of radioactive contamination. If the level of radioactive material in the water is less than 0.01mCi/ml (22,000 dpm/ml), the water will be disposed of to the sewer down designated sinks. This process will be continued until no further contamination of the solid material is detected. The solid material may then be disposed of as regular non-radioactive trash, or returned to use.

4. Aqueous liquids contaminated with long (>120 days) half lived materials will be separated from organic liquids.

Scintillation waste is no longer regulated by the NRC as radioactive material and may be disposed of according to the nature of the organic material. It is recommended that biodegradable Scintillation Fluid be used in which case the material may be disposed of to the sewer (down designated-by the RSO- sinks in the laboratories.)

Organic waste must be packaged and shipped under the supervision of the Radiation Safety Officer to a licensed radioactive waste disposal facility. Please ensure that this category of waste is kept to a minimum.

Aqueous liquids will be disposed of as described in #3 (above) if the level of radioactive material in the liquid is less than 0.01mCi/ml (22,000 dpm/ml).

5. Radioactive material with physical half-lives longer than 120 days, that cannot be disposed of as described above (for example non-washable solid waste) will be packaged and shipped under the supervision of the Radiation Safety Officer to a licensed radioactive waste disposal facility. Please ensure that this category of waste is kept to a minimum.

6. Radioactive material with physical half-lives shorter than 120 days will be packaged and stored on site for ten half lives (143 days for
32P: 870 days for 35S). Solid waste will be disposed of in the regular trash after the removal of all radioactive material warning labels. Aqueous wastes will be disposed of to the sewer. Organic wastes will be disposed of as non-radioactive organic waste.

7. Investigators will initiate waste minimization practices. These should be discussed with the RSO. Costs for the disposal of radioactive waste are very high and it is to our advantage to maintain the levels of waste generated at Susquehanna University as low as possible.



CHAPTER SIX


EMERGENCIES

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In the event of an emergency that involves radioactive materials, the following actions are to be taken.

FIRE

1. Pull fire alarm and Public Safety at Ext. 4444. Provide information as to the location and type of fire, your name and telephone extension, and the presence of radioactive materials or hazardous chemicals in the affected area.

2. If appropriate, use nearest fire extinguisher

3. Use others, if possible, to assist in clearing the building.

4. Remain at the scene to provide assistance.

INJURY

1. Treat the medical injury first--there are no radioactive materials at Susquehanna University which present a life threatening

hazard.

2. If it is a minor injury, e.g. small cut, provide first aid.

3. If it is a major injury, e.g. broken leg, call Public Safety at Ext. 4444. Provide information as to the location and name of the injured individual, the nature of the injury, your name and telephone extension, and whether radioactive materials are involved.

4. Call the RSO (ext.4206) if radioactive materials are involved.

SPILL

 

 

 

 

 

1. Stop the source of the radioactive material spill.

2. Warn others in the area of the spill.

3. Isolate the area to prevent entry.

4. Minimize exposure by covering the spill and maintaining distance from the spill area (especially for 32P contamination).

5. Call the RSO (ext.4206) to discuss clean-up procedures.


CHAPTER SEVEN


SPECIFIC PROCEDURES FOR SPILLS

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SURFACE CONTAMINATION

1. Wear gloves to clean up any spill. First blot up any radioactive liquid (place soaked pads, etc. into a plastic bag.) Always wipe from the spill perimeter in toward the center of the spill. Discard towels when wet. When the area is dry, change gloves. Monitor the area to determine if any contamination remains and its extent (remember that spills can splash onto cabinets and other furnishings).

2. If contamination remains, reclean with soap and water, again working from the perimeter in toward the center. Monitor and repeat this process as often as necessary until no further reduction in count rate is seen. (A swipe test must be used for H-3 spills.)

3. Contaminated tools and equipment should first be thoroughly wiped with a damp soapy towel, then dried and monitored. If necessary, soak in a strong cleaning solution for several hours. Place the cleaning solution and first few rinses into the aqueous radioactive liquid waste container. Monitor and repeat the process if necessary.

4. Report spill to RSO.

PERSONNEL CONTAMINATION

1. Warn other personnel in the area.

2. Call the RSO (ext.4206) and Public Safety (ext. 4444) and remain in the area.

3. If skin is contaminated with radioactive materials, the following steps should be taken:

a. Carefully wash the affected area with plain soap and water. Use caution and minimal water so as not to spread the contamination. If the contamination is on areas of the body other than the hands or forearms, attempt cleaning using paper towels or gauze pads moistened with soapy water.

b. Survey the contaminated area and repeat step a, as needed. If skin begins to redden, cease cleaning efforts immediately.

c. For puncture wounds, run water over the puncture for several minutes, and let the wound bleed freely. Monitor the wound to determine the presence of contamination. If no contamination is detected, handle the wound in the usual manner for puncture wounds

4. If major contamination occurs and RSO not immediately available, remove affected clothing (including shoes), clean hands, and move to nearby unaffected area.


CHAPTER EIGHT


RADIOISOTOPE LABORATORY SAFETY RULES

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GENERAL RULES

1. No pipetting by mouth.

2. No food or beverages or applying of make-up in radioisotope labs.

3. Gloves and laboratory coat are required when using radioisotopes.

4. Prescribed personnel monitors must be worn (if required).

5. Hands, shoes, and clothing should be frequently monitored.

6. Work with radioactive materials is an approved hood or glove box, unless the safety of working on an open bench can be demonstrated.

7. Radioisotope work should be conducted in an impervious tray or pan, lined with absorbent paper.

8. Utilize shielding and distance whenever possible.

9. Dispose of liquid and solid radioactive waste in the approved containers provided.

10. Monitor radioisotope work areas frequently and after each radioisotope handling procedure. Record monitoring on Contamination Record sheet.

11. Thoroughly wash hands after handling isotopes, before eating or smoking, and on completion of work.

12. Maintain appropriate records of use, transfer, and disposal of radioactive materials.

13. Report accidental inhalation, ingestion, injury, or spills to your supervisor and the RSO.

14. Review pertinent safety practices frequently especially before using a new radionuclide.

15. Assure compliance with NRC, Code of Federal Regulations, Part 20
If you have any questions or need assistance call Extension 4206.

SAFE HANDLING OF RADIOACTIVE MATERIALS

Laboratories authorized to use and/or store radioactive materials must observe precautionary rules designed to minimize both internal and external radiation hazards:

PERSONNEL PROTECTION

1. Gloves and laboratory coat are required when handling radioactive materials.

2. Hands, shoes, clothing and the work area must be monitored frequently when handling radioactive materials. An operating survey meter should be placed adjacent to the workstation so that gloved hands can be checked frequently throughout the procedure. If a meter is not available or if tritium is being used, change gloves frequently.

3. Prescribed personnel monitors (film badge, ring dosimeter) must be worn (if required). If you want to know if dosimetry is appropriate for your level of radioactive exposure, contact the RSO.

4. Avoid contamination transfer from gloves to "clean" items by picking them up with a tissue or paper towel.

5. Avoid reflex actions such as reaching into a pocket or scratching an itch while wearing gloves.

6. Do not leave a laboratory without first removing gloves and surveying both hands and feet.

7. If contaminated items or vials containing radioactive samples must be transported to another location, carry the items in a box lined with an absorbent pad or on a cart. Elevators may not be used to transport radioactive materials.

8. Remove gloves in such a manner as to contain any contamination on them:

a. Grasp the glove on one hand near the wrist and gently pull it off.
b. Ball this glove into the fingers of the other hand.
c. With the free hand, grasp the remaining glove near the wrist and gently pull it inside out over the balled glove.
d. Drop the parcel into the solid radioactive waste container.

9. Thoroughly wash hands after handling isotopes, before eating or smoking, and on completion of work.

WORKPLACE PROTECTION

 

 

 

 

1. a. 32P/35S: Conduct radioisotope procedures on a fresh plastic-backed absorbent pad, regardless of whether the benchtop surface is already covered. Be certain that the absorbent side of the pad is facing up. Remove the pad following completion of the procedure and dispose of it as radioactive waste if it is contaminated.

b. Tritium: Work on a nonabsorbent drip tray, preferably made of stainless steel. Any drips or spills should be rinsed with water, the water tested for the level of contamination and if below 0.01mCi/ml (22,000 dpm/ml), then disposed of to the sewer down designated sinks.

2. Utilize drip trays to transfer vials, beakers, test tubes, syringes, etc. from one location to another.

3. Utilize small disposable benchtop cups at the workplace to receive pipet tips, etc. to avoid many individual movements to the large radioactive waste containers.

4 Label all containers and instruments used for radioisotope work with radioactive labeling tape.

5. Utilize shielding and distance whenever possible. Plexiglass shielding designed for P-32 use should be at least 3/8" thick.

6. Dispose of liquid and solid radioactive waste in the approved containers provided. See Chapter 5 for information on waste and disposal.

7. 10 CFR 20.207 requires that all radioactive materials be secured when unattended: i.e., radioisotope laboratories must either be locked when unoccupied or all radioactive material in them must be under lock and key.

MONITORING/DOSIMETRY


Monitoring of the workplace and of personal exposure is a important means of protection against the effects of radiation.

1. A bimonthly wipe-test with Scintillation counting (swipe test) of all work areas exposed to radioactive material will be performed by the RSO, or by a delegated individual. Contamination exceeding the action level of removable contamination (200dpm from a 100cm
2 area) will result in clean-up procedures being initiated. The PI's responsible for the contaminated areas will be notified and they will be responsible for the clean-up.

2. Seal sources of radioactive material shall be tested by the RSO, or by a delegated individual for leakage or contamination at intervals not exceeding six-months unless the material is in storage in which case it will be tested every three-years.

2. Work areas should be monitored for contamination before and after each procedure. In the case of
32P and 35S, this involves the use of the Geiger-Muller counter (the protective cover must be removed from the pancake probe when detecting 35S). Tritium (3H) contamination is only detectable by a swipe test. A table showing the parameters for use of various radiation survey instruments is included in the appendix.

3. Personal dosimetry (ring badges, film badges) will be required for individual workers who are expected to receive more than 10% of the allowable dose of 5rem/yr (whole body) or 50rem/yr (hands). Potential exposure levels should be discussed with the RSO. The responsibility for the costs associated with this dosimetry will be bourne by the PIs.


APPENDIX


GLOSSARY OF COMMON TERMS

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ABSORBED DOSE: The amount of energy imparted to matter by ionizing radiation per unit mass of irradiated materials (See RAD).
ABSORPTION: The absorption of energy from radiation passing through matter.
ACTIVITY: The number of nuclear disintegrations occurring in a given quantity of material per unit time (See Curie).
ALARA: As low as reasonably achievable.
ALPHA PARTICLE: A strongly ionizing particle emitted from the nucleus of massive atoms (Z>83)during radioactive decay, consisting of 2 protons and 2 neutrons with a double positive charge.
ANCILLARY PERSONNEL people entering radiologically restricted areas, but not for the purpose of working with radioactive material.
ANNIHILATION (ELECTRON): An interaction between a positive and negative electron; whereby their mass is converted into electromagnetic radiation.
ATOM: Smallest particle of an element that is capable of entering into a chemical reaction.
AUTORADIOGRAPH: Record of radiation from radioactive material in an
object made by placing the object in close proximity to a photographic emulsion.
BACKGROUND RADIATION: Background radiation is due to cosmic rays,
natural radioactivity, radioactive substances in building materials, etc.
BECQUEREL: One disintegration per second (abbreviated Bq).
BETA PARTICLE: Electron emitted from the nucleus of radioactive atom.
BIOASSAY. An indirect method of determining the radionuclides contained within the body.
BREMSSTRAHLUNG: Electromagnetic (x-ray) radiation association with the deceleration of charged particles passing through matter. Usually associated with energetic beta emitters, e.g., Phosphorus-32.
CALIBRATION: Determination of accuracy of a measuring instrument.
CONTAMINATION RADIOACTIVE: Deposition of radioactive material in any place where it is not desired.
COUNT (RADIATION MEASUREMENTS): A single detected event.
CRITICAL ORGAN: An organ or tissue that will experience the greatest hazard from irradiation.
CURIE: A quantity of any radioactive material in which the number of disintegrations is 3.7 x 1010 per second (abbreviated Ci). 3.7 x 1010 Bq.
Millicurie: One thousandth of a curie (3.7 x 107 disintegrations per second).
Abbreviated mCi. 3.7 x 10
7 Bq.
Microcurie: One millionth of a curie (3.7 x 104 disintegrations per second).
Abbreviated _Ci. 3.7 x 10
4 Bq.
Picocurie: One-millionth of a microcurie (3.7 x 10-2 disintegrations per second (2.22 disintegrations per minute)). Abbreviated pCi. 3.7 x 10-2 Bq.
DECAY,RADIOACTIVE: Disintegration of the nucleus of an unstable nuclide by the spontaneous emission of charge particles and/or photons.
DER: Department of Environmental Resources (state of Pennsylvania).
DOSE
,ABSORBED
: The energy imparted to matter by ionizing radiation
per unit mass of irradiated material at the place of interest. The unit of absorbed dose is the rad (100 ergs/gram), or the Gray,which is equivalent to 100 rad.
DOSE EQUIVALENT: A quantity used in radiation protection expressing
all radiation on a common scale for calculating the effective absorbed dose. The unit of dose equivalent is the rem, which is numerically equal to the absorbed dose in rads multiplied by certain modifying factors such as the quality factor, the distribution factor, etc. The Sl unit is the Sievert, Sv. 1 Sv equals 100 rem.
EFFICIENCY (COUNTERS): A measure of the probability that a count will be recorded when radiation is emitted.
ELECTRON CAPTURE: A mode of radioactive decay involving the capture
of an orbital electron by the nucleus. Often referred to as "K-capture" or "K-electron capture."
ELECTRON VOLT: A unit of energy equivalent to the amount of energy
gained by an electron in passing through a potential difference of a volt. Abbreviated eV. Larger multiple units of the electron volt frequently used are: KeV for thousand or kiloelectron volts, MeV for million electron volts and BeV for billion electron volts.
EXPOSURE: A measure of the ionization produced in air by x gamma radiation. The special unit of exposure is the Roentgen.
FILM BADGE: A packet or photographic film used for the measurement of radiation exposure.
GAMMA RAY: Penetrating electromagnetic radiation of nuclear origin. Except for origin, identical to x- ray.
GEIGER-MUELLER (G-M) COUNTER: Portable radiation detection instrument.
GENETIC EFFECT OF RADIATION: Mutations, produced by the absorption of ionizing radiations that can be passed on to offsprings.
GRAY: The Sl unit of absorbed does. 1 Gy equals 100 rad.
HALF-LIFE BIOLOGICAL: The time required for the body to eliminate one-half of an administered dose of any substance by the regular processes of elimination.
HALF-LIFE EFFECTIVE: Time required for a radioactive nuclide in a system to be diminished 50 percent as a result of the combined action of radioactive decay and biological elimination.

T1/2 eff= 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.
HALF VALUE LAYER (HALF-THICKNESS): The thickness of any specified material necessary to reduce the intensity of an x-ray or gamma ray beam to one-half its original value.
HEALTH PHYSICS: A radiological science dealing with the protection of personnel and the environment from harmful effects of ionizing radiation.
INVERSE SQUARE LAW: The intensity of radiation at any distance from a point source varies inversely as the square of that distance. For example: If the radiation exposure is 100 R/hour at 1 inch from a source, the exposure will be 0.01 R/hour at 100 inches.
IONIZATION: Removal of electrons from an atom by radiation interaction.
IONIZATION CHAMBER: An instrument designed to measure the quantity or ionizing radiation.
I
ONIZATION SPECIFIC: The number of ion pairs per unit path length of ionizing radiation in a medium; e.g., per centimeter of air or per micron of tissue.
IONIZING RADIATION: Any electromagnetic or particulate radiation capable of producing ions, directly or indirectly, in its passage through matter.
ISOTOPES: Nuclides having the same number of protons in their nuclei, and hence having the same atomic number, but differing in the number of neutrons, and therefore in the mass number. Almost identical chemical properties exist between isotopes of a particular element.
LABELED COMPOUND: A compound containing radioactive atoms.
MAXIMUM PERMISSIBLE DOSE (MPD): Maximum does of radiation that may be received by persons working with ionizing radiation.
MONITORING: Periodic or continuous determination of the amount of ionizing radiation or radioactive contamination present in a occupied region as a safety measure for purposes of health protection.
NEUTRON: Elementary particle with a mass approximately the same as that of a proton. A neutron is electrically neutral and will undergo radioactive beta decay when in a free state.
NRC: Nuclear Regulatory Commission.
NUCLIDE: A species of atom characterized by its mass number atomic number, and energy state of its nucleus.
PRINCIPAL INVESTIGATOR: The professor, instructor, or staff supervisor overseeing a research project involving radioactive material.
PROTECTIVE BARRIERS: Barriers of radiation absorbing material, such as lead or concrete, that are used to reduce radiation exposure.
Protective Barriers Primary: Barriers subjected to radiation in the direct beam.
Protective Barriers Secondary: Barriers subjected to stray or scattered radiation.
RADIATION: The emission and propagation of energy through space or through a material medium in the form of waves; (such as x-rays or gamma rays) or particles such as alpha and beta particles.
RADIATION ABSORBED DOSE (RAD): The unit of absorbed dose. Equal to 100 ergs/of energy per gram of material. 1000 mrad = 1 rad. 1 rad = .01 Gy.
RADIOTOXICITY: Refers to the potential of an isotope to cause damage to living tissue by absorption of energy from the disintegration of the radioactive material introduced into the body.
REM: The special unit of dose equivalent. The dose equivalent in rem is numerically equal to the absorbed dose in rads multiplied by the quality factor, distribution factor, and any other necessary modifying factors. 1000 mrem = 1 rem. 1 rem= 0.1 Sv.
RING BADGE: A badge worn on the finger to monitor exposure to the extremities of the body from radiation.
ROENTGEN (R): The quantity of x or gamma radiation such that the associated corpuscular emission per 0.001293 grams of dry air produces, in air, ions carrying one electrostatic unit of quantity of electricity of either sign (2.58 x 10-4 coulombs/kg). The roentgen is the special unit of exposure. 1000mR = 1R.
RSO: Radiation Safety Officer.
SCINTILLATION COUNTER: A counter in which light flashes produced in a scintillator by ionizing radiation are converted into electrical pulses by a photomultiplier tube.
SHIELDING MATERIAL: Any material which is used to absorb radiation and thus reduce its intensity. Lead, concrete, aluminum, water, and plastic are examples of commonly used shielding material.
SIEVERT: The Sl unit of dose equivalent. 1 Sv = 100 rem.
SMEAR (SMEAR OR SWIPE TEST): A procedure in which a swab, e.g., a circle of filter paper, is rubbed on a surface and its radioactivity measured to determine if the surface is contaminated with loose radioactive material.
SWIPE: Another name for smear.
SPECIFIC ACTIVITY: Radioactivity per unit mass or volume (e.g.,Ci/g; Ci/mmol).
SURVEY RADIOLOGICAL: Evaluation of a radiation hazard.
THERMOLUMINESCENT DOSIMETER: A dosimeter made of crystalline material that is capable of both storing absorbed energy from ionizing radiation and releasing this energy in the form of visible photons when it is heated. The amount of light released can be used as a measure of radiation exposure to these crystals.
USER: Personnel working with radioactive material or radiation generating devices.
X-RAYS: Penetrating electromagnetic radiations resulting from rapid deceleration of electrons or transitions of electrons from higher energy to lower energy orbitals.


APPENDIX

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Radiation inventory sheet

Inventory Control Number ________________________

Isotope (3H, 32P etc)________________ Chemical form________________________________

Lot #____________________________ Purchaser/tel #_______________________________

Date Received_____________________ Vial swipe dpm_____________ Room stored_________

Original Amount (mCi) ______________ Date Finished__________________________________


Date Activity Amount to Activity
Removed Waste Remaining



Please return the completed form to Dr. David S. Richard (Fisher 217, Tel 4206).


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Radiation Worker Training Form

This form must be completed and returned to Dr. David S. Richard before a worker is allowed to work with, or around radioactive material.

Name of Worker (student/physical plant)______________________________________________________

D.O.B._____________________ Date of training ______________________
M/F______________ If female, has the worker been informed of the Nuclear Regulatory Commission regulations regarding pregnancy? (Y/N) ______________

These regulations state that a women may "declare" her pregnancy in writing to the License holder. This declaration will be held on file. The licensee shall ensure that the dose to an embryo/fetus shall not exceed 0.5rem during the entire pregnancy. The woman shall be reassigned to other duties without penalty for the duration of the pregnancy (or until she "undeclares" the pregnancy in writing) if the dose is expected to exceed 0.5rem. These NRC regulations place the responsibility for the radiological safety of the pregnancy on the woman by requiring a written "declaration of pregnancy" before any action may be taken.


Please describe in detail the training provided to this worker in the space below. Please outline the responsibilities of the worker. Use the back of the page if necessary.























Worker Declaration: I have received and understand this training__________________________(sign/date)

Faculty Declaration: I have given the this training to the worker named above _________________(sign/date)

Radiation Safety Officer ______________________________ (sign/date)

Please return the completed form to Dr. David S. Richard (Fisher 217, Tel 4206).


 

 

 

Appendix :

 

Measures to correct equipment deficiencies.

 

1. Geiger Muller counter.

 

Used for 32P and 35S detection (the latter with the pancake probe cover removed). Use positive check source to determine if instrument is operational. If it is not, check that the probe is correctly attached and/or check/change the batteries, and check that the instrument is at the correct setting for isotope detection.

 

If this fails to work, send counter to Ludlum Measurements Inc., 501 Oak St., Sweetwater, Texas 79556, for repair. (Area 915 235 5494).

 

2. Beckman LS6500 Scintillation counter.

 

Used for 3H , 14C and 32P detection (the latter with no scintillation cocktail). If machine is apparently operational but no counts are detected, use a known positive sample (such as 3H standard) as control and/or check the user program.

 

Should this fail to work, call Beckman Service at 1 800 551 1150 (Mark Starr is our service rep).

 

service agreement # 923215-1

expiration date 11/30/00 (renewed anually)

Customer order # 96732

LS6500 ID# 237465

Serial #7067165

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