Understanding Radiation
Atomic Number and Atomic Mass
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- The illustration below shows the chemical symbol for the hypothetical element "X"
- The number of protons in the nucleus is represented by "Z", the atomic number
- All the isotopes of an element have the same "Z"
- The atomic mass of the element (number of protons plus the number neutrons) is represented by "A"
- "A" is usually placed to the left above the element symbol
- The number of neutrons in the nucleus is equal to A minus Z
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- Two different forms, or isotopes, of carbon are shown below:
- Carbon-12: with 6 protons and 6 neutrons and an atomic mass of 12
- Carbon-14: with 6 protons and 8 neutrons and an atomic mass of 14
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Adapted from Atomic Shorthand (EPA) |
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What Is the Decay Rate/Half-life of an Isotope?
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Understanding the Significance of a Range of Radiation Doses: Charts from DOE
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Radioactive Properties, Internal Distribution, and Risk Coefficients
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Isotopes of Interest: Properties, Treatment, and Fact Sheets
Information in this table adapted from:
- Management of Persons Contaminated with Radionuclides: Handbook (NCRP Report No. 161, Vol. I), National Council on Radiation Protection and Measurements, Bethesda, MD, 2008.
- Tochner ZA, Glatstein E, Internal Contaminant Radionuclides: Properties and Treatment (Table 216-1) in "Chapter 216: Radiation Bioterrorism," in Harrison's Principles of Internal Medicine, 17th Edition, Fauci AS, Longo DL, Kasper DL, Braunwald E, Jameson JL, Loscalzo J, Hauser SL, eds., pp. 1358-1364, McGraw Hill, 2008.
Isotope |
Ionizing radiation decay mode |
Radioactive half-life |
Biological half-life |
Major exposure pathways |
Focal accumulation |
Treatment: References for use |
Fact sheets
(CDC,
ATSDR,
EPA,
Argonne Natl. Lab) |
Americium (Am-241) |
α |
458 years |
73,000 days |
Inhalation Skin |
Lungs Liver Bone Bone marrow |
DTPA† * |
CDC
ATSDR
EPA
Argonne (PDF - 39 KB)
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Californium (Cf-252) |
α, γ |
2.6 years |
N/A |
Inhalation Ingestion |
Bone Liver |
DTPA* |
Argonne (PDF - 39 KB) |
Cesium (Cs-137) |
β, γ |
30 years |
70 days |
Inhalation Ingestion |
Follows potassium; renal excretion |
Prussian blue, insoluble† * |
CDC
ATSDR
EPA
Argonne (PDF - 39 KB)
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| Cobalt (Co-60) |
β, γ |
5.26 years |
9.5 days |
Inhalation |
Liver |
Succimer (DMSA)§ (DailyMed) DTPA* EDTA§ N-Acetyl-L-cysteine§ |
CDC
ATSDR
EPA
Argonne (PDF - 38 KB)
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Curium (Cm-244) |
α, γ, neutron |
18 years |
Liver: 7,300 days Bone: 18,250 days |
Inhalation Ingestion |
Liver Bone |
DTPA† * |
Argonne (PDF - 42 KB) |
| Iodine (I-131) |
β, γ |
8.1 days |
138 days |
Inhalation Ingestion Skin |
Thyroid |
Potassium iodide† *
Saturated solution of potassium iodide§
Propylthiouracil§
Methimazole§
Potassium iodate§ |
CDC
ATSDR
EPA
Argonne (PDF - 38 KB)
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Iridium (Ir-192) |
β, γ |
74 days |
50 days |
N/A |
Spleen |
Consider DTPA*
Consider EDTA§ |
CDC
Argonne (PDF - 95 KB)
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Isotope |
Ionizing radiation decay mode |
Radioactive half-life |
Biological half-life |
Major exposure pathways |
Focal accumulation |
Treatment: References for use |
Fact sheets
(CDC,
ATSDR,
EPA,
Argonne Natl. Lab) |
Phosphorus (P-32) |
β |
14.3 days |
1,155 days |
Inhalation Ingestion Skin |
Bone Bone marrow Rapidly replicating cells |
Hydration + Phosphate drugs
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| Plutonium (Pu-239) |
α |
2.2 x 104 years |
73,000 days |
Inhalation (limited absorption) |
Lung Bone Bone marrow Liver Gonads |
DTPA§
DFOA§
EDTA§
DTPA + DFOA§
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CDC
ATSDR
EPA
Argonne (PDF - 58 KB)
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Polonium (Po-210) |
α |
138.4 days |
60 days |
Inhalation Ingestion Skin |
Spleen Kidneys Lymph nodes Bone marrow Liver Lung mucosa |
Gastric Lavage
Dimercaprol (BAL)*
Succimer (DMSA)§ (DailyMed)
D-Penicillamine§ (DailyMed)
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CDC
Argonne (PDF - 41 KB)
HPS (PDF - 492 KB)
NRC
More references
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| Radium (Ra-226) |
α, β, γ |
1,602 years |
16,400 days |
Ingestion |
Bone |
Aluminum hydroxide*
Barium sulfate*
Sodium alginate§
Calcium phosphate§
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ATSDR
EPA
Argonne (PDF - 52 KB)
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| Strontium (Sr-90) |
β |
28 years |
18,000 days |
Inhalation Ingestion |
Bone |
Inhalation:
Calcium gluconate§
Barium sulfate§
Ingestion:
Rx is the same as for radium (see above). Additional Rx may include stable strontium compounds:
Strontium lactate§
Strontium gluconate§
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CDC
ATSDR
EPA
Argonne (PDF - 39 KB)
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Isotope |
Ionizing radiation decay mode |
Radioactive half-life |
Biological half-life |
Major exposure pathways |
Focal accumulation |
Treatment: References for use |
Fact sheets
(CDC,
ATSDR,
EPA,
Argonne Natl. Lab) |
Thorium (Th-232) |
α |
1.41 x 1010 years |
Bone: 8,030 days Liver/total body: 700 days |
Inhalation Ingestion |
Bone |
Consider DTPA* |
ATSDR
EPA
Argonne (PDF - 49 KB)
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| Tritium (H-3) |
β |
12.5 years |
12 days |
Inhalation Ingestion Skin |
Whole body |
Water diuresis* |
EPA
Health Protection Agency (UK)
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| Uranium (U-235) |
α |
7.1 x 108 years |
15 days |
Ingestion |
Kidneys Bone |
Sodium bicarbonate*
For high level intake consider off-label diuretics and/or dialysis§ |
CDC
ATSDR
EPA
Argonne (PDF - 46 KB)
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| Yttrium (Y-90)¶ |
β |
64 hours |
N/A |
Inhalation Ingestion |
Bone |
DTPA*
EDTA§ |
Argonne ¶ (PDF - 39 KB)
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References for use
† FDA approved: Countermeasures so marked have been approved as treatment for internal contamination with the listed radioisotope by the US Food and Drug Administration (FDA).
* NCRP preferred: Countermeasures so marked have been listed as preferred treatments for internal contamination with the listed radioisotope by the National Council on Radiation Protection and Measurements [Management of Persons Contaminated with Radionuclides: Handbook (NCRP Report No. 161, Vol. I)]. Except where noted, use of these countermeasures has not been approved by the US Food and Drug Administration (FDA).
§ NCRP suggested: Countermeasures so marked have been listed as suggested treatments for internal contamination with the listed radioisotope by the National Council on Radiation Protection and Measurements [Management of Persons Contaminated with Radionuclides: Handbook (NCRP Report No. 161, Vol. I)]. Use of these countermeasures has not been approved by the US Food and Drug Administration (FDA).
See also:
More Polonium-210 references
¶ For Yttrium-90 radioactive properties and health concerns, see Strontium-90 Human Health Fact Sheet
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Radiation Units of Measure
| Unit | Abbreviation | Definition | Comment |
| Roentgen |
R |
The amount of energy absorbed in air |
For x-rays and gamma rays only |
| Radiation absorbed dose |
rad |
The energy absorbed per gram of material
1 rad = 100 ergs/gram |
Important because it represents the amount of energy that is absorbed by the material of interest-e.g., person, organ, tissue, cells |
| Roentgen equivalent man |
Rem |
The product of the amount of energy absorbed (rad) times the efficiency of radiation in producing damage
rem = rad x (Wr) |
Accounts for the different degrees of damage produced by equal doses of different radiations, for example:
Radiation
Radiation Weighting Factor (Wr)
x rays
gamma rays
beta particles
1
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| Gray* |
Gy |
1 Gy = 100 rad |
1 Gy = 1 joule/kilogram |
| Sievert* |
Sv |
1 Sv = 1 Gy x Wr |
1 Sv = 100 rem |
| Curie |
Ci |
The number of radioactive decays (disintegrations)/ unit of time |
1 Ci = 2.2 x 1012 disintegrations/minute
1 Ci = 3.7 x 1010 disintegrations/second
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| Becquerel* |
Bq |
The number of radioactive decays (disintegrations)/ unit of time |
1 Bq = 60 disintegrations/minute
1 Bq = 1 disintegration/second
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* International units (SI) of Bequerel, Gray and Sievert are the currently favored expressions.
Adapted from:
Program on Technology Innovation: Evaluation of Updated Research on the Health Effects and Risks Associated with Low Dose Radiation (PDF - 903 KB) (Electric Power Research Institute [EPRI] document 1019227, Table 2-1, page 42, November 2009)
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Radiation Unit Conversion Factors
Unit of measure |
Conversion equivalent |
| 1 curie |
= 3.7 x 1010 disintegrations/second |
| 1 becquerel |
= 1 disintegration/second |
| 1 millicurie (mCi) |
= 37 megabecquerels (MBq) |
| 1 rad |
= 0.01 gray (Gy) |
| 1 rem |
= 0.01 sievert (Sv) |
| 1 roentgen
(R) |
= 0.000258 coulomb/kilogram (C/kg) |
| 1 megabecquerel (MBq) |
= 0.027 millicuries (mCi) |
| 1 gray
(Gy) |
= 100 rad |
| 1 sievert
(Sv) |
= 100 rem |
| 1 coulomb/kilogram
(C/kg) |
= 3880 roentgens |
Adapted from Measurement - Activity: How Much Is Present? (Radiation Emergency Assistance Center/Training Site (REAC/TS))
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Radiation Unit Prefixes
| Multiple |
Prefix |
Symbol |
1012 |
tera |
T |
109 |
giga |
G |
106 |
mega |
M |
103 |
kilo |
k |
102 |
centi |
c |
10-3 |
milli |
m |
10-6 |
micro |
μ |
10-9 |
nano |
n |
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How to do a Survey for Radiation Contamination
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- Survey with Geiger-Mueller Detector
- Probe held about 1/2 inch from surface
- Move at a rate of 1 to 2 inches per second
- Follow a systematic pattern (see below)
- Document readings in counts per minute (CPM) on a body chart (PDF - 49 KB)
- Compare radiation survey results before and after decontamination procedure
- Use nuclear medicine and radiation therapy technologists or others familiar with the use of radiation detection instruments
- Goal is < 2 times background radiation reading
- In general, areas that register more than twice the previously determined background radiation level are considered contaminated.
- For accidents involving alpha particle emitters, if the reading is less than twice the background radiation level, the person is not contaminated to a medically significant degree. If the accident circumstances indicate that an alpha particle emitter (such as plutonium) or low-energy beta emitter could be a contaminant, a health physicist should always be consulted.
- Specifics of the survey
- Have the person stand on a clean pad.
- Instruct the person to stand straight, feet spread slightly, arms extended with palms up and fingers straight out.
- Monitor both hands and arms; then repeat with hands and arms turned over.
- Starting at the top of the head, cover the entire body, monitoring carefully the forehead, nose, mouth, neckline, torso, knees, and ankles.
- Have the person turn around; repeat the survey on the back of the body.
- Monitor the soles of the feet.
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Adapted from How to Detect Radiation (Radiation Emergency Assistance Center/Training Site (REAC/TS))
See also: Video: Screening People for External Contamination: How to Use Hand-held Radiation Survey Equipment (HHS/CDC) 
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Annual Limits of Intake (ALIs) for Radioactive Isotopes in the Workplace
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Radioisotope |
Chemical Form |
Retention Time |
Ingestion ALI (μCi) |
Inhalation ALI (μCi) |
Americium-241 |
All compounds |
Weeks |
8 x 10-1 |
6 x 10-3 |
Cesium-137 |
All
compounds |
Days |
1 x 102 |
2 x 102 |
Cobalt-60 |
All compounds, except |
Weeks
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5 x 102
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2 x 102
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oxides, hydroxides, halides, nitrates |
Years |
2 x 102 |
3 x 101 |
Iodine-125 |
All compounds |
Days |
4 x 101 |
6 x 101 |
Iodine-131 |
All compounds |
Days |
3 x 101 |
5 x 101 |
Iridium-192 |
All compounds, except |
Days
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9 x 102 |
3 x 102 |
halides, nitrates, metallic iridium |
Weeks |
...
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4 x 102 |
oxides, hydroxides |
Years |
...
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2 x 102 |
Palladium-103 |
All compounds, except |
Days |
6 x 103 |
6 x 103 |
nitrates |
Weeks |
...
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4 x 103 |
oxides, hydroxides |
Years |
... |
4 x 103 |
Phosphorus-32 |
All compounds, except |
Days
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6 x 102 |
9 x 102 |
phosphates of Zn2+, S3+, Mg2+, Fe3+, Bi3+; lanthanides |
Weeks |
...
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4 x 102 |
Plutonium-239 |
All compounds, except |
Weeks
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8 x 10-1 |
6 x 10-3 |
PuO2 |
Years |
...
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2 x 10-2 |
Radium-226 |
All compounds |
Weeks
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2 x 100 |
6 x 10-1 |
Strontium-90 |
All soluble compounds except SrTiO3 |
Days
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3 x 101 |
2 x 101 |
All insoluble
compounds and
SrTiO3 |
Years |
...
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4 x 100 |
Tritium (Hydrogen-3) |
Water |
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8 x 104 |
8 x 104 |
Uranium-233 |
UF6, UO2F2, UO2(NO3)2 |
Days
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1 x 101 |
1 x 100 |
UO3, UF4, UCI4 |
Weeks |
...
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7 x 10-1 |
UO2, U3O8 |
Years |
...
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4 x 10-2 |
Uranium-234 |
UF6, UO2F2, UO2(NO3)2 |
Days
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1 x 101 |
1 x 100 |
UO3, UF4, UCI4 |
Weeks |
...
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7 x 10-1 |
UO2, U3O8 |
Years
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... |
4 x 10-2 |
Uranium-235 |
UF6, UO2F2, UO2(NO3)2 |
Days
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1 x 101 |
1 x 100 |
UO3, UF4, UCI4 |
Weeks |
...
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8 x 10-1 |
UO2, U3O8 |
Years
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... |
4 x 10-2 |
Yttrium-90 |
All compounds, except |
Weeks
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4 x 102 |
7 x 102 |
oxides, hydroxides |
Years |
...
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6 x 102 |
1 Adapted from Annual Limits on Intake (ALIs) and Derived Air Concentrations (DACs) of Radionuclides for Occupational Exposure (Appendix B to 10 CFR Part 20, Nuclear Regulatory Commission)
According to the introduction to Appendix B of the reference above, "The ALIs and DACs for inhalation are given for an aerosol with an activity median aerodynamic diameter (AMAD) of 1 μm and for three classes (D,W,Y) of radioactive material, which refer to their retention (approximately days, weeks or years) in the pulmonary region of the lung."
For soluble mixtures of U-234, U-235 (and U-238) in air, chemical toxicity may be the limiting factor.
NRC Listing of ALIs by Isotope (NRC)
NCRP has published new, detailed guidance on Management of Persons Contaminated With Radionuclides: Handbook3 (NCRP Report No. 161, Volume I, Bethesda, MD, 2008). It recommends a new operational quantity, "Clinical Decision Guide" (CDG), as a replacement for ALI. CDG is designed "to provide a measure that physicians can use when considering the need for medical treatment for internally-deposited radionuclides or as a screening tool...". The new guidance updates NCRP Report No. 65: Management of Persons Accidentally Contaminated with Radionuclides (National Council on Radiation Protection and Measurements, Bethesda, MD, 1980)
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Allowable Limits of Radiation for the General Public and Radiation Workers
Exposure Limits
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Intended to Protect |
Nuclear Regulatory
Commission
(NRC)
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Occupational
Safety and Health Administration
(OSHA) |
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Non-occupational
Exposure Limits (General Public)
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Whole body |
100 mrem in a year
2 mrem in an hour
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N/A
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Occupational
Exposure Limits
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Whole body |
5 rem/year |
1.25 rem/quarter |
Lens of eye |
15 rem/year |
1.25 rem/quarter |
Skin |
50 rem/year |
7.5 rem/quarter |
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Extremities |
50 rem/year |
18.75 rem/quarter |
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Embryo/fetus |
500 mrem/gestation |
N/A |
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Minors (< 18 years) |
10% of adult annual dose |
10% of adult quarterly dose |
Exposure limit values in this table exclude exposures to natural sources of ionizing radiation (e.g., radon, cosmic radiation) and therapeutic or diagnostic medical sources of ionizing radiation (e.g., radiation therapy, nuclear medicine scans, arteriograms, x-rays, CT scans, etc.).
NRC provides guidance
concerning allowable limits of exposure to personnel/employees at facilities
using licensed sources (i.e., radiation workers) at workplaces like nuclear
power plants, industrial food irradiation facilities, and nuclear medicine and
radiation oncology departments. NRC also provides guidance on allowable
limits of exposure to the general public concerning any exposure to manmade
sources of radiation.
OSHA regulations only concern workplace or occupational exposures to ionizing radiation.
These limits apply to exposures to the general public from manmade sources of ionizing radiation (e.g., to people living in the vicinity of a nuclear power facility).
A maximum lifetime occupational dose (for adults) is defined as ≤ 5 x (N - 18) rem, where N = age in years at last birthday.
References:
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Common Radiation Exposures vs. Exposures in Radiation Events |
Common medical and
natural background sources of radiation |
Approximate dose in rem |
| Chest x-ray |
up to 0.03 |
| Average annual dose from cosmic radiation to people living in Rocky Mountain States |
0.06 - 0.08 |
| Average annual dose from cosmic radiation to flight crew members |
0.16 |
| Average annual dose from exposure to natural sources of ionizing radiation to the US population (e.g., radon, cosmic rays) |
0.2 - 0.3 |
| CAT scan (whole body) |
1 |
| Recommended annual occupational exposure limit, excluding personal medical exposures and exposures from natural sources |
up to 5 rem per year |
Adverse health effects from higher dose exposures,
including those possibly found after radiation events |
Approximate dose in rem |
| No symptoms |
15 |
| No symptoms of illness; minor and temporary drop in counts of white blood cells and platelets
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50 |
| Possible Acute Radiation Syndrome; 10% of exposed individuals may have nausea/vomiting within 48 hours and a mild drop in blood counts |
100 |
| 50% of exposed individuals will die within 30 days in the absence of appropriate medical care (LD 50/30) |
300 - 400 |
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Adapted from: Hall EJ. Radiobiology for the Radiologist. Lippincott Williams & Wilkins, 2000
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Exposure of the US Population to Ionizing Radiation
- The US population is exposed to various sources of ionizing radiation1-4, both naturally occurring and man-made.
- Ubiquitous, naturally occurring radiation: e.g., radon in homes, radiation from space, radionuclides in the body, naturally occurring terrestrial (ground) radiation, other. See Illustration of Background Radiation
- Medical tests and procedures: e.g., patients exposed to radiation during diagnostic tests and treatments
- Consumer products and activities involving radiation: e.g., building materials, commercial air travel by passengers, cigarette smoking, other
- Occupational exposure to workers: e.g., medical, aviation, commercial nuclear power, industry, commerce, other
- Miscellaneous sources: e.g., nuclear power generation, Department of Energy installations, decommissioning and radioactive waste, other
- Experts have devised a formula to calculate the annual dose of ionizing radiation from all these sources for the average individual in the US and for the US population as a whole1-4
- Annual US effective dose was calculated for the year 20061-4
- REMM discusses effective dose to provide some context for interpretation of possible risks from radiation in a radiation mass casualty emergency.
- Key EPA information about radiation doses in the US
References:
- Ionizing Radiation Exposure of the Population of the United States (NCRP Report 160), National Council on Radiation Protection and Measurements, Bethesda, MD, March 2009, Chapter 1.
- Mettler FA, Bhargavan M, Faulkner K et al. Radiologic and nuclear medicine studies in the United States and worldwide: frequency, radiation dose, and comparison with other radiation sources--1950-2007. Radiology. 2009 Nov; 253(2):520-31. Epub 2009 Sep 29. [PubMed Citation]
- Recommendations of the International Commission on Radiological Protection, ICRP Publication 60, Ann. ICRP 1991; 21(1-3)
- Recommendations of the International Commission on Radiological Protection, ICRP Publication 103, Ann. ICRP 2007; 37(2-4)
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