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Curie or Becquerel
Unit for measuring radioactivity
1 Ci = 3.7×1010 Bq
1 mCi = 1×10-3 Ci
1 MBq = 1×106 Bq
1 mCi = 37 MBq
Roentgen or Coulomb/kg
Measurement of Exposure
(1 R = 2.58×10-4 C/kg)
Rad or Gray
Measurement of Absorbed Dose
(1 Rad = .01 Gy)
Roentgen Equivalent Man or Sievert
Measurement of Dose Equivalent
(1 Rem = .001 Sv)
Radioactivity
The rate of energy emitted as radiation, as atoms disintegrate/decay over some amount of time (eg seconds or minutes). Measured in Ci or Bq.
1 Ci = 3.7×1010 dps, or 2.2×1012 dpm
1 Bq = 1 dps, or 60 dpm
Exposure
Amount of electrical charge (coulomb) in some amount of air (eg. kg) due to ionizing radiation from the interaction with gamma or x-rays. Measured in R or C/kg.
1 R = 2.58×104 C/kg of air
Absorbed Dose
The amount of energy that is absorbed by some substance (or organism!) per unit mass (eg. kg or g). This absorbed energy (ionizing radiation) is deposited by radioactive sources. Measured in Rad or Gy.
1 Rad = 100 ergs of energy per gram of absorbing material
1 Rad = 0.01 Gy
1 Gy = 100 Rads
Dose Equivalent
Biologic harm imparted onto tissue from ionizing radiation given off by some radioactive source material. A combined measurement of the type of radiation absorbed by tissue, and the resulting medical effects. Measured in Rem or Sv.
1 Rem = 0.01 Sv or 10 mSv
1 Sv = 100 Rem
Equation for Dose Equivalent
H = D x QF
H = dose equivalent (Rem)
D = absorbed dose (Rad)
QF = Quality factor (dependent on type of radiation)
True/False: Exposure, measured in R, is applicable to all types of radiation.
False! The Roentgen only applies to gamma and x-rays, not to particulate radiation like beta decay or neutron emission.
True/False: Absorbed Dose, measured in Rad, applies to only certain materials and types of radiation.
False! Unlike the Roentgen (R), the Radiation Absorbed Dose (Rad) can apply to any form of radioactive decay (gamma, beta, etc.). Likewise, while the R only applies to radiation in the air, the Rad is applicable to any material it interacts with.
Occupational Dose
The dose received by those who work with radioactive materials, and are routinely exposed to ionizing radiation. The NRC’s safe limit for such workers is set at 5000 mrem (50 mSv) per year.
True/False: The Occupational Dose does not apply to radiation received outside of a job site.
True! Specifically, Occupational Dose excludes:
Natural background radiation (eg UV radiation on a sunny day)
Individual medical exposures (eg the dental x-ray at your yearly appointment)
Exposure to someone who has been administered radioactive material and released (eg a relative who recieved I-131 therapy for hyperthyroidism)
Exposure due to voluntary participation in medical research
Any other exposure encountered as a member of the public (look, one time I ate uranium yellow cake. I had to skip lunch that day and was like, the tiredest I’d ever been in my life)
Tracking exposure on a job site
If a worker is likely to receive more than 10% of the NRC occupational dose limit in 1 year, they must wear some type of dosimeter badge to “log” the radiation exposure.
Thermal Luminescent Dosimeters (TLD)
A dosimeter badge that contains Lithium Fluoride chips that absorb energy given off by ionizing radiation to which they are exposed. When heated, the chips release the absorbed energy as light.
Whole Body Badge
Thermal Luminescent badge worn from the neck to waist, where a worker will receive the most exposure to ionizing radiation.
Ring Badge
Thermal Luminescent badge worn by those who handle radiopharmaceuticals. Should be worn on the dominant hand, with the label facing inward towards the palm.
TLD badge function
In a TLD badge, one or more of the Lithium Fluoride chips is partially covered by a filter to distinguish between “non-penetrating” doses (skin/shallow), and “penetrating doses” (whole body/deep). The chips are inside of a light-tight holder, but when heated, they produce light. The brighter the light, the greater the dose was absorbed.
True/False: TLD Badges can measure any form of radiation exposure
False! TLD badges measure beta, gamma, and x-rays. But those the ones you need to worry about, anyway.
True/False: A ring badge only contains one Lithium Fluoride chip
True! I mean look at it, it’s tiny
Optically Stimulated Luminescence Dosimeter
A dosimeter badge that contains a thin layer of Aluminum Oxide or Beryllium Oxide that absorbs energy given off by ionizing radiation to which it is exposed. When subjected to optical stimulation, it emits a light signal proportional to the radiation absorbed.
True/False: OSL badges are “one and done”
False! OSL badges can be re-read, unlike TSL badges
Deep Dose Equivalent (DDE)
Dose equivalent at tissue depth of 1 cm. Applies to external whole-body exposure.
5 rem, or 50 mSv
Shallow Dose Equivalent (SDE)
Dose equivalent at tissue depth of 0.007 cm. Applies to external exposure of skin or extremity.
Committed Dose Equivalent (CDE)
Dose to some specific organ or tissue. Applicable to internal exposures.
Total Dose Equivalent
Sum of the DDE (external) and CDE (internal).
5 rem, or 50 mSv
NRC Occupational Dose Annual Limit for Whole Body
5 rem or 50 mSV
Also referred to as Total Effective Dose Equivalent (TEDE)
NRC Occupational Dose Annual Limit for Any Organ
50 rem or 500 mSv
Sum of Deep Dose Equivalent (DDE) + Committed Dose Equivalent (CDE)
NRC Occupational Dose Annual Limit for the Eye Lens
15 rem, or 150 mSv
Also called Lens Dose Equivalent (LDE)
NRC Occupational Dose Annual Limit for Skin/Extremities
50 rem, or 500 mSv
Also referred to as Shallow Dose Equivalent (SDE)
NRC Occupational Dose Annual Limit for Minors
10% of adult worker limits (eg 0.5 rem or 5mSv for TEDE, compared to 5 rem/50mSv for adults)
NRC Occupational Dose Annual Limit for the Public
0.1 rem, or 1 mSv
NRC Occupational Dose Annual Limit for Pregnant Workers
0.5 rem, or 5 mSv for duration of pregnancy
Pregnancy must be declared in writing
NRC Dose Equivalent in any Unrestricted Area
2 mrem/hour, or 0.02 mSv/hour
ALARA
Reducing radiation exposure to workers “As Low As Reasonably Achievable”. Set at 10% of NRC limits, checked every 3 months by the site RSO.
ALARA Quarterly Limits for Whole Body
Level I = 125 mrem (1.25 mSv)
Level II = 375 mrem (3.75 mSv)
Monthly = 42 mrem (0.42 mSv)
ALARA Quarterly Limits for Extremities
Level I = 1250 mrem (12.5 mSv)
Level II = 3750 mrem (37.5 mSv)
Monthly = 420 mrem (4.2 mSv)
Methods of Radiation Protection
Wear lab coat and monitor it before going to lunch or taking it home
Glove up when handling radioactive materials and practice hand hygeine
Don’t eat/drink/use cosmetics OR store these items in an area with radioactive materials
Conduct weekly wipe tests to find contaminated areas
Open vials of NaI-131 under a fume hood (it is volatile and gives off vapors) and perform Xenon ventilation studies in negative pressure rooms
Methods of Controlling External Exposure
Time: don’t stick around in radiation areas, like the hot lab, and try to work as efficiently as possible
Distance: Keep as far as possible from radiation sources, including patients after injection. You can also use tongs when calibrating doses.
Inverse Square Law
(I1)(D1²) = (I2)(D2²)
I = Intensity of source/Exposure rate, D = Distance from source
Shielding
The use of various materials to prevent/reduce passage of ionizing radiation from a source to an area that needs to be protected.
Plastic shielding is usually enough for Beta emitters
Higher-energy Positron emitters require tungsten or lead shielding
How to use Shielding
Syringe shields when drawing/administering doses
Lead pigs when transporting those doses
Lead bricks to surround the generator and the L-block where radiopharms. are stored
Drawing doses and changing needles behind the L-block because it has a lead window, which reduces eye exposure
Portable lead shields in rooms where you can’t move away from your radioactive patient while scanning. Rooms for PET patients must have substantial lead lining in the walls!
Lead-lined walls and waste bins in storage areas
Half Value Layer (HVL)
The amount of lead (or other material) needed to reduce radiation exposure
HVL of Lead against Tc 99m = 0.2 mm thick lead shielding
Shielding Equation
I = (I0)(e^(-μx))
I = Intensity after shielding, I0 = before shielding
e = base of natural log 2.718
u = attenuation coefficient (0.693/HVL in cm)
X = thickness of shield (cm)
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Radioactive spill procedure
Yap about it
Isolate the area and cover the spill with absorbent paper to prevent spread
Neb for contamination - shoes, hands, clothes. Remove the uncontaminated persons
Remove contaminated clothes/shoes/etc and place in plastic bag
Rinse contaminated body areas with warm water and wash with soap
Yap to the RSO
Wear PPE (coat, gloves, booties) to clean up with absorbent paper. Put the contaminated paper in the radioactive waste bin
Check areas/persons/etc with the radiation survey meter
GM counter
Geiger-Muller counter. Used for detecting low-level radiation.
Gas-filled
Sensitive enough to detect levels of radiation close to background, but has high “dead time” making it not useful for high radiation areas
Can check received packages, and detect contamination during daily surveys
Test daily with the included Cs-137 source, and calibrate annually
Ionization Chamber
Used for detecting high-radiation areas.
Gas-filled
No “dead time” because it only collects one ion pair for every one radiation event, but less sensitive for low-level radiation areas
Can be used to survey exposure rates in adjacent rooms and I-131 patients prior to release
Calibrate annually
Well Counter
Used to test for small amounts of removable radioactivity.
Contains an NaI crystal with a hole drilled into it to hold test tubes
Used for wipe tests on recieved packages, weekly department wipe tests (for removable contaimination), semi-annual wipe tests on sealed sources, and to assay blood samples during DTPA renal scan (determine GFR)