| Name | Definition | Abreviation |
|---|---|---|
| Millicurie | 1/1,000 Ci | [mCi] |
| Microcurie | 1/1,000,000 Ci | [uCi] |
| Nanocurie | 1/1,000,000,000 Ci | [nCi] |
| Picocurie | 1/1,000,000,000,000 Ci | [pCi] |
Whenever it is impossible or impractical to remove a source of radiation, other means must be considered for purposes of personnel protection. Three factors which determine the total exposure one receives in a given radiation field are:
1. Time of exposure.
2. Distance from Source.
3. Amount of shielding present.
The following is an excerpt from the Federal Register / Vol 51, No. 6 / Jan 9, 1986:
(Page 1126):
Dose control terms:
(1) "ALARA" (acronym for "As low as is reasonably achievable") means making every reasonable effort to maintain exposures to radiation as far below the dose limits in this part as is practical: (i) Consistent with the purpose for which the licensed activity is undertaken, (ii) taking into account the state of technology, the economics of improvements in relation to benefits to the public health and safety, and other societal and socioeconomic considerations, and (iii) in relation to utilization of nuclear energy in the public interest.
(Page 1130):
20.102 As low as is reasonably achievable levels of exposure.
(a) Each licensee shall ensure that the dose to individuals receiving occupational doses and to members of the public is as low as is reasonably achievable (ALARA) and does not exceed the appropriate limits.
Procedures and engineering controls based on sound radiation protection principles and practices should be used, to the extent practical, to reduce potential exposures.
| Units | Disintegrations / Second| microcurie | 3.7 x 104 | millicurie | 3.7 x 107 | picocurie | 3.7 x 10-2 | |
|---|
In normal protection work the product of absorbed dose and quality factor (QF) expresses the irradiation
in terms of a common scale for all ionizing radiations.
| Type of Radiation | Quality Factor(QF)| X-ray, gamma ray, beta particles | 1 | Alpha particles | 10 | Heavy recoil atoms | 20 | Neutrons | 2 to 10.5 | |
|---|
In regard to protection purposes the term QF replaces the former term RBE (relative biological effectiveness); in order to talk about RBE one must define exposure conditions as well as the effect studied.
Much effort has been directed toward the problem of calculating the dose which a person receives as a result of internally deposited radionuclides. Among the many factors of main concern that enter into such a calculation are: the shape of the organ, the type of radiation and the distribution of the deposit. The distribution factor (DF) is used to correct for non-uniform distribution in the case of internally deposited radionuclides. Thus, the dose equivalent becomes:
| Milliroentgen | 1/1000 R | [mR] |
|---|
The special unit of exposure rate is Roentgen per hour, or milliroentgens:
A simple formula for use in Health Physics applications to estimate the exposure rate at a distance of one meter from a known isotropic point source of activity C [Ci] and energy E [MeV] for an energy range form .2 MeV to 2 Mev in air is:
The tube then goes into a quenching mode. Basically it turns off and returns to its normal state so that it can start over again. While the quenching mode can be measured in milliseconds, this lag time reduces its efficiency as compared to the scintillation detector.
Advantages of the Geiger-Mueller are that it is very rugged and inexpensive, as compared to other detector types.
1. The biological half-life: It is the time required for the body to eliminate one-half of the amount of a radioactive substance internally deposited by excretion, exhalation and perspiration.
2. The effective half-life: It is defined as the time required for the radioactivity from a given amount of radioactive substance deposited in the tissues or organs to diminish by 50 % as a result of the combined action of radioactive decay and loss of the material by biological elimination. The effective half-life is usually experimentally determined.
| Radioactive Material | Lead | Steel | Concrete |
|---|---|---|---|
| 60Co | 0.49" | 0.87" | 5.0" |
| 137Cs | 0.25" | 0.68" | 2.1" |
| 192Ir | 0.19" | 0.50" | 1.9" |
| 131I | 0.14" | 0.37" | 1.4" |
or
I x D2 = i x d2
(Where I = intensity at a distance (D) from a point source, and i = intensity at a distance (d) from the
same source).
Example: If the exposure rate at 1 meter equals 100 mR/hr then the exposure rate at 2 meters equals 25 mR/hr.
| Radioactive Isotope | mR/hr @ 3' | mR/hr @ 6' | mR/hr @ 9' |
|---|---|---|---|
| 192Ir | 61 | 15.25 | 6.8 |
| 131I | 25 | 6.25 | 2.8 |
Another advantage of the scintillation detector is that it can differentiate energy levels in the counts. Thus it can be calibrated for use in spectrum analysis.
On the down side, scintillation detectors are expensive as compared to Geiger - Mueller's and they are not very rugged.
Penetrating electromagnetic radiation whose wave lengths are shorter than those of visible light. They are usually produced by bombarding a target (metallic) with fast electrons in a high vacuum. In nuclear reactions, it is customary to refer to photons originating in the nucleus as Gamma Rays and those originating in the extranuclear parts of the atom as X-rays. They are sometimes referred to as Roentgen rays after Wilhelm Conrad Roentgen, the discoverer. The only difference between X and gamma radiation is the source.
See Dose Equivalent (Roentgen's Equivalent to Man)
