Basic Radiation Safety Training
for Users of Radioactive Materials
Texas A&M Health Science Center
Environmental Health and Safety
Rev. 07-2014
Agenda
• Introduction
– Regulatory structure
– Rad safety program
• What is radiation?
– Types of radiation
– Standard isotopes used
– Biological effects of
radiation
– Background radiation
– Radiation detection
• HSC Procedures
–
–
–
–
–
Package Receiving
Waste Handling
Safety (PPE, storage, etc)
Spill/Contamination
Survey Procedure
REGULATORY STRUCTURE
Line of Authorization
• US NRC
– Delegates responsibilities
to TDSHS
• TDSHS
– Issues licenses and ensures
compliance within the
state
• HSC
– Radiation Safety Officer
(RSO) and Radiation
Committee (RSC) oversee
institutional compliance
Line of Authorization
• HSC
– Holds multiple “Site licenses” for radioactive
materials usage on our campuses
– RSO and RSC
• Create, review, and approve the institutional radiation
safety manual
• Create review and approve new principal investigators
(PIs) to become radioactive materials permittees
• RSO and RSC approved new permits are submitted to
TDSHS for final approval
EHS website
http://www.tamhsc.edu/ehsm/index.html
HSC Radioactive Materials Permit
RADIATION BASICS
Radiation Basics
• Bohr model of the atom
– Protons
• +1 charge
• Located in nucleus
– Neutrons
• 0 charge
• Located in nucleus
– Electrons
• -1 charge
• Located in orbits
Radiation Basics
Isotopes of Carbon
Radiation Basics
Radiation Basics
•
A
Chemical
Z
•
6
Li
3
Symbol
• Layout for nuclear notation
– A: mass number
(protons+neutrons)
– Z: atomic number
(number of protons)
• Example of nuclear notation
– Generally the “Z” number is
not included
RADIOACTIVE DECAY
Radioactive Decay
•
•
•
•
•
•
•
•
Alpha particle
Beta particle
Positron
X ray
 ray
Neutron
Proton
Electron
14
Radioactive Decay
• Definition
– Any spontaneous change in the state of the nucleus
accompanied by the release of energy.
• Major Types
– alpha () particle emission (decay)
– beta () particle emission (-), positron emission (+) and
orbital electron capture (ec)
– gamma () decay including internal conversion
Radioactive Decay
Radioactivity and radioactive properties of nuclides
are;
 Determined by nuclear considerations only
 Independent of the chemical and physical states
of the radioisotope
 Unique to the respective radionuclide
Radioactive Decay
• Electron Volt
– is the unit normally used for expressing the energy
possessed by ionizing radiation
– (the amount of energy gained by a single electron moving
across a 1 volt potential)
• Linear Energy Transfer (LET)
– is the average energy deposited over a unit of distance for
a given absorber expressed in keV/cm.
Radioactive Decay
•
Ionizing
•
•
•
•
Alpha
Beta
Gamma
Non-Ionizing
–
–
–
–
–
Microwaves
Sunlight
Infrared waves
Radio waves
Lasers
Radioactive Decay
Radioactive Decay
Alpha particles in a cloud chamber
Radioactive Decay - Alpha
• Helium Nucleus
• Very heavy elements
Radioactive Decay - Alpha
• Certain heavy nuclei, usually with Z > 83, decay by
emitting an alpha particle, written as α, or 2He4
• This particle consists of two protons and two
neutrons, it is like a helium nucleus. Its ejection from
the nucleus moves the daughter nuclei toward
stability.
210 → He4 +
206
Po
Pb
84
2
82
Radioactive Decay - Alpha
• Range in Air: 0 – 4 cm
Radioactive Decay - Alpha
Alpha Decay Energy
Decay Scheme
Electron Tracks
Radioactive Decay - Beta
• Nuclides with an excess
number of neutrons
• Same as orbital
electrons but originates
in the decaying nucleus
Radioactive Decay - Beta
Radioactive Decay - Beta
Radioactive Decay – Beta Shielding
Bremsstrahlung Radiation
• Charged particles must radiate electromagnetic energy
whenever they experience a change in velocity (either in
speed or direction)
• These are x rays emitted when high-speed charged particles
suffer rapid acceleration
Bremsstrahlung Radiation
Radioactive Decay – Gamma
•
•
•
•
No mass or charge
Form of EM radiation
“Packets” of energy
Differ from x-rays only in origin
Radioactive Decay – Gamma
•
•
•
•
No mass or charge
Form of EM radiation
“Packets” of energy
Differ from x-rays only
in origin
Electromagnetic Spectrum
Radioactive Decay – Gamma
• Gamma rays are
emitted in specific
energies characteristic
to the parent nuclide
• Most often, they
require lead or concrete
as a shield
60
60
𝐶𝑜 →
𝑁𝑖 + 𝛽 + 𝛾
27
28
Radiation Penetration
Radioactive Decay – Neutron
• No charge
• Interacts by kinetics (slams into nucleus)
• Very unlikely in a laboratory environment without specialized
equipment
• Difficult to shield (best shielded by hydrogen)
• Water
• Lots of plastic
• Concrete
• Parafin
• Very dangerous
Tritium – 3H
Long Lived Radionuclide
• Half-life: 12.32 years
• Type of Emitter: Beta
• Beta Energy: 0.0186 MeV
• Travel Distance in Air:
0.61 cm : 0.24 inches
• Travel Distance in
Tissue: Insignificant
• ALI(inhalation) 80 mCi
• ALI(ingestion) 80 mCi
The major concern with using 3H is
internal exposure. 3H cannot be
readily monitored during its use, as
with a survey meter, therefore,
special precautions are needed to
keep the work environment clean.
Many tritium compounds readily
migrate through gloves and skin
because of the chemical compound.
Carbon – 14C
Long Lived Radionuclide
• Half-life: 5730 years
• Type of Emitter: Beta
• Beta Energy: 0.156 MeV
• Travel Distance in Air:
24.2 cm : 9.54 inches
• Travel Distance in Tissue:
Insignificant
• ALI( inhalation) 2 mCi
• ALI(Ingestion) 2 mCi
• Some 14C labeled compounds can
penetrate gloves and skin.
• Wearing two pairs of gloves and
changing the outer pair every
fifteen or twenty minutes will
reduce the chances of absorption
through the skin
• A survey meter with a GM probe
is not likely to detect the
presence of 14C in amounts less
than about 50 µCi due to low
detection efficiency
Phosphorus – 32P
Long Lived Radionuclide
• Half-life: 14.28 days
• Type of Emitter: Beta
• Beta Energy: 1.709 MeV
• Travel Distance in Air:
6.10 m : 240 inches
• Travel Distance in Tissue:
0.8 cm : 0.31 inches
• ALI( inhalation) 0.4 mCi
• ALI(Ingestion) 0.6 mCi
Phosphorus – 33P
Long Lived Radionuclide
• Half-life: 25.3 days
• Type of Emitter: Beta
• Beta Energy: 0.249 MeV
• Travel Distance in Air:
0.89 cm : 35 inches
• Travel Distance in Tissue:
Insignificant
• ALI( inhalation) 6 mCi
• ALI(Ingestion) 3 mCi
• Millicurie (37 MBq)
quantities of 33P do not
present a significant
external exposure hazard
– low-energy betas emitted
barely penetrate gloves and
the outer dead layer of skin.
• Uptakes of 33P are assumed
to be retained with a
biological half-life of 0.5
days.
Sulphur – 35S
Long Lived Radionuclide
• Half-life: 87.2 days
• Type of Emitter: Beta
• Beta Energy: 0.167 MeV
• Travel Distance in Air:
25.4 cm : 10.2 inches
• Travel Distance in Tissue:
Insignificant
• ALI( inhalation) 0.02 mCi
• ALI(Ingestion) 0.006 mCi
• Some compounds
tagged with 35S are
volatile and care should
be taken when opening
the primary vial.
• Depending on the
activity in-use, shielding
or finger dosimeters
may be required.
Iodine – 125I
Long Lived Radionuclide
• Half-life: 60.14 days
• Type of Emitter: Gamma
• Gamma Energy: 0.0355
MeV
• Travel Distance in Air:
135 m : 443 ft
• Travel Distance in Tissue:
• ALI( inhalation) 0.06 mCi
• ALI(Ingestion) 0.04 mCi
Physical Half-Life
The time required for a radioactive substance to loose
50 percent of its activity by decay.
Each radionuclide has an unique half-life.
Radioactive Decay - Half-life
𝐴 𝑇 = 𝐴0 ×
−(𝜆)(𝑡)
𝑒
AT = Activity at some time T
A0 = Original Activity
e = Natural Log
 = Decay Constant = 0.693 / T1/2
t = Elapsed Time
Radioactive Decay - Half-life
Example:
One month ago (30 days) a vial of 35S – dATP was received in your lab
containing 1.2 mCi. For an experiment you will be doing today, you need
0.750 mCi. If no 35S – dATP was removed from the vial, will you have
enough?
(T1/2 for 35S = 87.9 days)
AT =
A0 =
𝜆 =
t =
Activity at some time T
1.2 mCi
Decay Constant = 0.693 / 87.9 days = 0.00788 d-1
30 d
𝐴 𝑇 = 1.2𝑚𝐶𝑖 × 𝑒 −(0.00788)(30) = 1.2mCi × 0.789
= 0.947𝑚𝐶𝑖
Radioactive Decay - Half-life
• Biological half-life is the time it takes for a substance
(drug, radioactive nuclide, or other) to lose half of its
original amount through normal biological excretory
routes.
• Effective half-life denotes the halving of radioactive
material in a living organism by means of radioactive
decay and biological excretion.
𝑡𝑝 𝑡𝑏
𝑡𝑒 =
𝑡𝑝 + 𝑡𝑏
Radioactive Decay - Half-life
UNITS & DEFINITIONS
USED IN RADIATION
Unit
Abbreviation
Curie
dps
dpm
Curie
Ci
1
3.7 E+10
2.22 E+12
Millicurie
mCi
1 E-3
3.7 E+7
2.22 E+9
Microcurie
𝜇Ci
1 E-6
3.7 E+4
2.22 E+6
Nanocurie
nCi
1 E-9
3.7 E+1
2.22 E+3
Picocurie
pCi
1 E-12
3.7 E-2
2.22 E+0
Activity:
The rate of decay of a radioactive sample, i.e. by the
number of atoms that decay per unit time.
Units & Definitions - Activity
International Unit of Activity
• Becquerel (Bq)
– 1.00 Bq = 1 dps
– 60.00 Bq = 1 dpm
– 1.00 Ci = 3.7 x 1010 Bq
Units & Definitions - Exposure
Roentgen R the unit of exposure to Ionizing Radiation. The amount of γ or xray radiation required to produce 1.0 electrostatic unit of charge in 1.0 cubic
centimeter of dry air.
Use the abbreviation “R/hr” or “mR/hr” when measuring an x-ray, gamma, or beta
dose.
Units & Definitions – Dose
RAD (radiation absorbed dose) is a unit of
measurement used to describe the amount of
energy transferred from a source of ionizing
radiation to any material, including human tissue.
• As a unit of exposure, 1 rad means that each gram of air at 0°
C and 1 atmosphere has absorbed 100 ergs of energy.
• As a unit of dose, 1 rad means that each gram of exposed
tissue has abosorbed 100 ergs of energy.
Units & Definitions – Dose
Different types of ionizing radiation cause differing degrees of
biological effects even when the same amount of energy is
transferred.
To create a universal measurement, the “rad” is multiplied by
the specific quality factor for a type of ionizing radiation to
determine the dose equivalent.
The rate at which an individual is exposed (i.e. an hour verses a
lifetime) also influences the level of biological harm.
Use a dosimeter to measure a dose equivalent.
Units & Definitions – Quality
Factor
•
•
•
Used to relate the absorbed dose of
various kinds of radiation to the
biological damage caused to the
exposed tissue
Radiation Type
Quality Factor
(QF)
X-rays, Gamma rays, Beta
particles
1
Necessary because the same
amounts absorbed of different kinds
of radiation cause different degrees
of damage
“Slow” Neutrons, ≤ 10 keV
3
“Fast” Neutrons, ≥ 10 keV
10
Converts the absorbed dose to a unit
of dose equivalence to compare
damage caused by any kind of
radiation
Protons
10
Alpha particles
20
Units & Definitions – Dose
Dose Equivalent Rem (Roentgen Equivalent Man) is the dose equivalent
for tissue, and takes into account the varying amount of damage to tissue based
on the energy and radiation type, and accounts for tissue sensitivity or the risk of
malignancy from the radiation induced injury.
The dose equivalent can be determined by applying a tissue weighting factor (risk
factor) to the absorbed dose (rad).
Use the abbreviation “Rem/hr” or “mRem/hr” when measuring an x-ray, gamma, or
beta dose.
BIOLOGICAL EFFECTS OF
IONIZING RADIATION
Effects of ionizing radiation
Excitation
Ionization
Effects of ionizing radiation
Radiation Induced Decomposition of Water within a cell
• H2O can form the following:
–
–
–
–
–
–
–
–
–
H2O+
H2
H+
H0
OHOH0
HO2
H2O2
e-
• Free radicals within the cell can result in indirect effects
Harderian Wasp Eggs
Effects of ionizing radiation
• DNA damage can result from radiation
– Single and double strand breaks
– Most often repaired successfully by the cell
Potential Outcomes of Radiation Damage to Parent Cells
Effects of ionizing radiation
Law of Bergonie & Tribondeau (1906)
Determinants of Radiosensitivity
Law states that radiosensitivity varies:
1. Directly with rate of cell division
(more metabolically active = more radiosensitive)
2.
Directly with number of future divisions a cell will undergo
(younger cells are more radiosensitive)
3.
Inversely with the degree of cellular differentiation
(stems cells are the most radiosensitive)
Effects of ionizing radiation
Radio-sensitive Cells
Radio-resistant Cells
Reproductive Cells
Bone, Cartilage, Muscle
Blood forming tissues
Liver
Epithelium of skin
Kidney
Epithelium of gastrointestinal tract
Nerve tissue
Effects of ionizing radiation
Biological Effect Parameters:
1. Radiation Type
2. Rate of Exposure / Absorption
3. Area Exposed (Variation in Cell Sensitivity)
4. Variation in Species and Individual Sensitivity
Effects of ionizing radiation
• In summary, radiation may:
–
–
–
–
Interact within the body
Deposit energy in the body
Create ionizations in the body
Cause DNA damage
• All of which may lead to biological damage, but:
– Damage may be repaired
– Damage may be benign
– Damage may be neutralized through apoptosis
RADIATION PROTECTION
Radiation Protection
Philosophy
• Radiation doses are
kept as low as possible
• Stems from Linear-NonThreshold dose model
• ALARA program
required by Federal and
State regulations
Radiation Protection
Keys to ALARA
• Time
• Distance
• Shielding
• Housekeeping
Radiation Protection
The INDIVIDUAL working with radioactive
material
MUST
assume the RESPONSIBILITY for their own safety
AND
must ensure that their actions do not result in a
hazard to others.
Natural Background
Natural Background
Natural Background
Natural Background
Natural Background
Natural Background
Natural Background
Natural Background
Natural Background
Risk versus Dose models
Radiation Risk in Perspective
Health Physics Society Position Statement (March 1996):
• Radiogenic health effects (Primarily cancer) are observed in
humans only at high doses.
• Below this dose, estimation of adverse health effects is
speculative since risk of health effects are either too small to
be observed or are non-existent.
• Epidemiological studies have not demonstrated adverse
health effects in individuals exposed to small doses (less than
10 rem) delivered in a period of many years
Radiation Protection
Maximum Permissible Dose Limits
Whole Body
Lens of eye
Skin
5 Rem / year
15 Rem / year
50 Rem / year
Minor (under 18 y/o)
0.5 Rem / year
Unborn Child of Worker
0.5 Rem over entire
gestation period of DPW
Members of the General Public
0.1 Rem / year
Radiation Protection
• 100,000 rad -Molecular
destruction
• 1,000 rad – 100% of people die:
CNS syndrome
• 450 rad – LD50 (50% of people
die)
• 50 rem/yr – extremity
regulatory limit
• 15 rem/yr – lens of the eye
regulatory limit
• 10 rem/yr – “whole body”
exposure causes measurable
blood changes
• 5 rem/yr – whole body
regulatory limit for trained
radiation workers
• 4.167 rem/qtr – HSC extremity
administrative dose limit
• 1.25 rem/qtr – HSC lens of the
eye administrative dose limit
• 0.417 rem/qtr – HSC whole
body administrative dose limit
RADIATION DETECTION
Detecting Radiation
• Not detectable by any of our natural five sense
• Requires specialized equipment
• Varying types of equipment for different types of
radiation and the type of measurements desired
• Knowledge of the technology is key to making sure
that you know which detector to choose to which
situation
Gas Filled Detectors
Gas Filled Detectors
•
Geiger-Mueller detectors can be used
to survey for a variety of different
radioisotopes. Pancake probe GM
detectors (shown on the bottom
right) are the most efficient type of
GM detectors and should be used
when available.
Gas Ionization Curves
Scintillators
Photomultiplier tube
Sodium Iodide Probe
Liquid Scintillators
Liquid Scintillators
Liquid Scintillators
Liquid Scintillators
• Racks should be loaded
on the right with the first
vial at the very back
• Counting goes in counterclockwise direction
• Keeps counting until the
de-activated flag comes
back to the front
– Will usually do one more
loop through just to be
sure it caught everything
Liquid Scintillators
The liquid scintillation counter
is the only commonly available
radiation detector capable of
detecting tritium. The liquid
scintillation counter may be
used to detect any removable
radioactive contamination.
Liquid Scintillators
• Scintillation Cocktail
– Use biodegradable counting media
– Old cocktail may cause problems
– Keep samples in the dark
Liquid Scintillation
“Flag” Out
“Flag” In
Liquid Scintillators
• The protocols shown on
each flag are defined in the
software
• Look for the corresponding
protocol number on the
computer to determine
which protocol flag you will
need
• Existing protocols can be
customized and new
protocols can be created as
needed up to the highest
numbered protocol flag
available
Counting Efficiency
Counting efficiency is the
calibration of count rate in a
specific detector where to
quantify and express the
observed count rate in units
of radioactivity
Cpm/dpm = efficiency
Each isotope of interest has
it own counting efficiency
Standard Efficiencies of LSC and GM
Type of
Radiation
Energy (MeV)
Efficiency
LSC
Efficiency
GM
Tritium
-
0.0186
45%
0%
Carbon-14
-
0.157
85%
10%
Phosphorus-32
-
1.709
95%
45%
Phosphorus-33
-
0.249
85%
20%
Sulfur-35
-
0.167
85%
10%
Calcium-45
-
0.258
90%
20%
-
0.032
20%
2%

0.035
-
0.606
95%
20%

0.364
Isotope
Iodine-125
Iodine-131
PROCEDURES
Safety Procedures
1.
2.
3.
4.
5.
Program Procedures (Ordering / Receiving / Waste)
Disposal of Radioactive Materials
Internal / External Exposure Protection Methods
Laboratory Procedures
Emergency Response
Radioactive Packages
• Radioactive materials can be shipped on US
roadways under certain conditions
– Federal regulations govern placarding
– Container qualifies as a Type A container
– Placarding:
•
•
•
•
Exempted Package
White 1
Yellow 2
Yellow 3
Exempt package
Packages containing radioactive material can be classified as exempt if the
dose rate on-contact, at one meter, and if the concentration of material within
is below a certain threshold
Non Exempt package: White 1
White 1 packages may have an on-contact dose rate not to exceed 0.5
mrem/hour and no detectable dose rate at one (1) meter
Non Exempt package: Yellow 2
Yellow 2 packages may have an on-contact dose rate not to exceed 50
mrem/hour and a detectable dose rate at one (1) meter not to exceed 1 mrem
/hour
Shipping label
The address must include the RSO or Site Safety Officer’s name so that
EHS will be notified to pick up and perform the acceptance procedure.
Radioactive Packages
Radioactive Packages
Radioactive Packages
Radioactive inventory transfer
Transfer of RAM
Contact the RSO for information
Radioactive Waste
Radioactive waste must be segregated by form:
• Dry and Semi-Solid
• Sharps
• Liquid
• Scintillation Vials
• Biological
Radioactive Waste
Dry and Semi-Solid Waste Disposal
• Container for disposal: Plastic Bags
• Requirements:
–
–
–
–
Deface or remove container labels
Be careful not to tear bag
Bag must be sealed before calling EHS
Shield if necessary
• Separate by half-life (isotope)
Radioactive Waste
Sharps Waste Disposal
• Container for disposal: Sharps
Container
• Requirements:
– Do not overfill
– Take care when placing sharps in box
Radioactive Waste
Sharps Waste Disposal
• “Pipette Tip Sharps”: Plastic jug
• Applies to plastic micro-pipette tips
– Tips can puncture the bags used in
solid waste bin
• Requirements:
– Once full, place in solid radioactive
waste bin
Radioactive Waste
Liquid Waste
• Container:
– RSO approved plastic
carboy
• Requirements
– DO NOT OVERFILL CARBOY
• keep liquid level below
80%
– Provide double
containment (spill tray)
– First rinse
– Adjust pH
Radioactive Waste
Liquid Scintillation Vials
• Container for disposal
– Trays
– Bulk – box lined with a plastic bag
• Requirements
– Only biodegradable LS Fluid
Radioactive Waste
Biological waste (contaminated with RAM)
• Container
– Plastic bags, carboys, sharps containers
• Requirements
– Autoclave or chemically treat pathogenic and infectious waste
– DO NOT autoclave if contamination will be spread in autoclave
– Contact RSO with questions
Radiation Safety
• External exposure sources
– Mitigated by:
•
•
•
•
Time
Distance
Shielding
Housekeeping (efficient processes/procedure design)
• Internal exposure sources
– Mitigated by:
• Housekeeping (efficient processes/procedure design)
• Hygiene
• Containment
Radiation Safety
• Dedicated workspace
–
–
–
–
Absorbent paper covering the work surface
Survey meter
Spill tray
Dedicated tools
Radiation Safety
• Equipment that is dedicated or “exclusive use”
for radioactive material does not need to be
surveyed for contamination after each use
unless it is to be released for unrestricted use
• It must stay in the marked “rad use area”
Well prepared work space
This experimental setup is completely contained within a spill tray
covered with absorbent paper. If a spill were to occur, it would be
immediately contained and could be cleaned very easily.
Well prepared work space
The beta shield is placed within the spill tray. In the event the primary
vial was spilled, the liquid would be contained. The addition of absorbent
paper to this example is preferred as it would simplify cleanup.
Radiation Safety
Personal Protective Equipment (PPE)
• Eye Protection
• Lab Coat
• Gloves
• Complete coverage on legs
• Closed toed shoes
• Prohibited:
– Shorts
– Open toed shoes
– Half-shorts
Radiation Safety
•
•
•
•
•
PPE is useless if not used properly
DO NOT eat or drink in the lab
DO NOT scratch or rub your face or eyes
DO NOT put your gloved hands into your pockets
DO NOT use your gloved hands to operate any equipment that you may
use normally when not wearing gloves such as:
• Computers
• Phones
• Light switches
• Lab equipment
• Transport carts or trolleys
• Anything you touch while wearing gloves could become contaminated and
expose you, your friends, your family, or your coworkers to harm.
Dosimetry
• Primary dosimeter is either
a OSL or TLD badge
• Sensitive to gamma and
hard beta radiations
• Provides RSO with dose
information on a quarterly
basis
• Does not provide
information during a real
time exposure to radiation
Dosimetry - Badge
• Dosimeter badges
should be worn on
either the lapel or waist
– Whichever is closest to
the source of radiation
Dosimetry - Ring
• Your ring badge will come with your name on it. Wear the
badge with the name plate facing the source of radiation
• Be sure to wear the ring badge under your gloves to capture
actual dose to your skin
Safe Practices and Procedures
• Eating, drinking, application of cosmetics
PROHIBITED
• Mouth pipetting PROHIBITED
• Cover cuts, scrapes
• Do not use food containers for storage
• Keep personal items in the labs to a minimum
Safe Practices and Procedures
Storage:
• RAM must be stored
behind two locks
– Outer most door to
building does not count
• Plastic Containers
• Label containers
• Secure storage areas
when unattended
Safe Practices and Procedures
• Some compounds of I125
and S35 are volatile and
may become airborne
when the primary vial is
opened or during the
experiment.
• Volatile compounds
should be stored in a
dedicated RAM fume
hood where possible.
Safe Practices and Procedures
• Keep hands away from face,
head, etc.
• Monitor during use.
• After Procedure:
–
–
–
–
Promptly dispose waste
Return source vials
Store Samples
Post-Procedure Surveys:
• Survey meter (GM or similar)
• Swipe test using LSC
Safe Practices and Procedures
• Clean any contamination immediately
• Submit to Bioassays as required.
– Tritium (3H)
• use of uncontained 3H in > 8 mCi
– Iodine (125I)
• Equipment Repair
• Transportation between lab floors
• No PPE permitted outside of lab
Safe Practices and Procedures
• In the event of a spill, remember the acronym
SPILL:
– Stop
• Working get your thoughts together and don’t panic
– Presume
• Everything is contaminated until proven otherwise
– Inform
• Others about the spill
– Localize
• The spilled material to contain the spill
– Label
• Or cordon off the area to limit access
Safe Practices and Procedures
• Consult HSC eduSafe or
Emergency Flipchart and
Manuals
• If injuries occur, they take
first priority
– Call 911
– Provide first aid
– Monitor individual for
contamination
Response to Radioactive Spill
Area Decontamination
1. Identify boundaries of
spill
2. Absorb as much liquid
as possible
Response to Radioactive Spill
Area Decontamination
3. Start from outside of
the spill area moving
inward
4. Re-Survey
5. Repeat if needed
Response to Radioactive Spill
Area Decontamination
6. Place ALL paper towels
in radioactive waste.
7. Survey yourself (gloves,
lab coat, shoes)
Response to Radioactive Spill
Final Confirmation
8. Perform swipe test with LSC to measure removable
contamination.
9. Action Levels:
1. LSC results < 200dpm/100cm2 – “not contaminated”
2. LSC results > 200dpm/100cm2 – “contaminated” – requires re-cleaning
3. LSC results > 1000dpm/100cm2 – “Controlled Surface Contamination
Area (CSCA)” requires marking
Procedures
Skin Contamination
• Use mild soap
• Lukewarm water
• Re-monitor
• Repeat if needed
• Bioassay
Procedures
Potentially Contaminated Wounds
• Treat as Contaminated
• Monitor
• Flush with copious amounts of water
• Seek Medical Attention as needed
Procedures
Clothing Contamination
• Prevent further contamination
• Place in plastic bag
• Call RSO
Detector Use
Detector Use
1. Turn
meter
on
2. Battery
check
Detector Use
3. Audio on
4. Fast/Slow
response
5. Sensitivity
setting
Detector Use
6. Check Response
7. Obtain Background
8. Survey
- Move slowly over surfaces
- Have probe about ¼ inch off
surface
9.
10.
11.
12.
Contamination (2 x bkg)
Decontaminate or Store
Repeat
Record
Incident Reporting
• Report the following to EHS
– Personnel Contamination
– Area Contamination* (not readily removed)
– Release to the Environment
– Exposure to the General Public
Swipe Survey Process
Standard industry practice requires coverage of 100 cm2 in any
single swipe
Swipe Survey Process
• A swipe survey result is considered to be “positive for
contamination” if the LSC returns a result of 200 dpm
or greater on a swipe.
• It is important to number your samples and mark the
number on the survey map so that you can return to
the contaminated area to clean it.
• Re-run “positive” samples to rule out false-positives.
• Samples that are still positive after second run should
be considered confirmed positive and will require
cleaning.
Swipe Survey Process
Final Confirmation
• Perform swipe test with LSC to measure removable
contamination.
• Action Levels:
• LSC results < 200dpm/100cm2 – “not contaminated”
• LSC results > 200dpm/100cm2 – “contaminated” – requires re-cleaning
• LSC results > 1000dpm/100cm2 – “Controlled Surface Contamination
Area (CSCA)” requires marking
Swipe Survey Process
SUMMARY
Three Cardinal Rules For Working
With Radioactive Materials
Rule No. 1: Keep your radioactive material
where it belongs.
• Keep them well-marked throughout your experiment
• Keep them in a secured area inside laboratory
• Take precautions against spreading contamination by using
good hygiene
• Routinely checking your laboratory surfaces for
contamination
• Check yourself, especially your hands, for contamination
after every use of radioactive material.
Three Cardinal Rules For Working
With Radioactive Materials
Rule No. 2: Tell us if you have a problem.
– If you think you have radioactive material on your skin or
clothes, or
– if you have a spill that has any potential for being spread,
especially if it gets on the floor, call Safety immediately.
Three Cardinal Rules For Working
With Radioactive Materials
Rule No. 3: Document where your radioactive
material ends up when you are done with it.
– You should know where the radioactive material ends up
when you use it
– If you don't know, ask your PI, or lab manager
– You must document this information on Isotope Tracking
Sheets and Waste Forms
– This information is required for license records
Special Rules (Pregnancy)
– A woman is only pregnant when she submits the paperwork.
– Tighter dose restrictions are applied to protect the baby (no more
than 0.5 rem over the course of the pregnancy – 10CFR20)
– A woman has the right to declare and undeclare at any time.
Declared Pregnancy
Security
– Do not be afraid to challenge ANYONE you do not recognize in your
lab or lab area.
• Unauthorized personnel should not be in your lab. Asking for
identification is appropriate in all circumstances.
– No one other than authorized users should have access to RAM
– Keep all RAM in a locked refrigerator or cabinet
Summary
• What is radiation?
–
–
–
–
–
Types of radiation
Standard isotopes used
Biological effects of radiation
Background radiation
Radiation detection
• HSC Procedures
–
–
–
–
–
Package Receiving
Waste Handling
Safety (PPE, storage, etc)
Spill/Contamination
Survey Procedure
Contact Information
• Radiation Safety Officer
– Erich Fruchtnicht
– fruchtnicht@tamhsc.edu
– 979-436-0551
• Bryan EHS Officer
– Marc Goldsmith
– goldsmith@tamhsc.edu
– 979-436-0559
• Temple EHS Officer
– Cristina Alvarez
– calvarez@tamhsc.edu
– 254-742-7024
• Houston EHS Officer
– Stephanie Colman
– colman@tamhsc.edu
– 713-677-7953
• Dallas EHS Officer
– Hiram Patterson
– hpatterson@bcd.tamhsc.edu
– 214-828-8301
Test
•
•
•
•
Go to: http://www.tamhsc.edu/ehsm/radiation-safety.html
Click on “Radiation Safety Training Refresher Test”
Take test
Click submit