AFI-48-125(AF-dosime..
AFI-48-125(AF-dosime.. AFI-48-125(AF-dosime..
40 AFI48-125 1 MARCH 1999 result of employment in an occupation involving the use of radioactive material or equipment capable of producing ionizing radiation. overexposure (quarterly or annual)—Any accumulated or one-time ionizing radiation exposure exceeding the limits specified in 10 CFR. Permit—A written authorization to possess and use radiation sources issued by AFMOA/SGOR under the provisions of NRC Air Force Master Material License. Person—Any individual, corporation, partnership, firm, association, trust, estate, public or private institution, group, Government agency other than the NRC or the DoE subject to the licensing and related regulatory authority of the NRC and/or the Air Force Master Material License. planned special exposure (PSE)—An exposure that occurs infrequently during normal operations when it is necessary to permit a worker to receive doses in excess of the annual dose equivalent limits. Evaluate dose-limiting provisions for planned special exposures separately from and in addition to the dose-limiting conditions for normal exposure conditions. AFMOA/SGOR must approve all planned special exposures beforehand. public dose—The dose received by a member of the public from exposure to radiation and/or radioactive material released by a licensee, or to any other source of radiation under the control of the licensee. Public dose does not include occupational dose or doses received from background radiation, from any medical administration the individual has received, or from voluntary participation in medical research programs. Quality Factor (Q)—The modifying factor shown in Table A1.2. that is used to derive dose equivalent from absorbed dose. If it is more convenient to measure the neutron fluence rate than to determine the neutron dose equivalent rate in rems per hour or sieverts per hour, as provided in paragraph (b) of this section, 1 rem (0.01 Sv) of neutron radiation of unknown energies may, for purposes of the regulations in this part, be assumed to result from a total fluence of 25 million neutrons per square centimeter incident upon the body. If sufficient information exists to estimate the approximate energy distribution of the neutrons, the licensee may use the fluence rate per unit dose equivalent or the appropriate Q value from Table A1.3. to convert a measured tissue dose in rads to dose equivalent in rems.
AFI48-125 1 MARCH 1999 41 Table A1.2. Radiation Quality Factors. Type of Radiation Quality Factor(Q) Absorbed dose equal toa unit dose equivalenta X-, gamma, or beta 1 1 Alpha particles, multiple-charged particles, fission fragments and 20 0.05 heavy charge particles of unknown Neutrons of unknown energy 10 0.1 High-energy protons 10 0.1 a Absorbed dose in rad equal to 1 rem or the absorbed dose in gray equal to 1 sievert. Table A1.3. Neutron Quality Factors. Neutron Energy (MeV) Quality Factora(Q) Fluence per unitDose equivalentb(neutrons cm -2 rem -1 (Thermal) 2.5 X 10 -8 2 980 X 10 6 1 X 10- 7 2 980 X 10 6 1 X 10- 6 2 810 X 10 6 1 X 10- 5 2 810 X 10 6 1 X 10- 4 2 840 X 10 6 1 X 10- 3 2 980 X 10 6 1 X 10- 2 2.5 1010 X 10 6 1 X 10- 1 7.5 170 X 10 6 5 X 10- 1 11 39 X 10 6 1 11 27 X 10 6 2.5 9 29 X 10 6 5 8 23 X 10 6 7 7 24 X 10 6 10 6.5 24 X 106 14 7.5 17 X 10 6 20 8 16 X 10 6 40 7 14 X 106 60 5.5 16 X 10 6 1 X 102 4 20 X 10 6 2 X 102 3.5 19 X 106 3 X 102 3.5 16 X 106 4 X 102 3.5 14 X 106
- Page 1 and 2: BY ORDER OF THE SECRETARY OF THE AI
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- Page 5 and 6: AFI48-125 1 MARCH 1999 5 Chapter 1
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- Page 15 and 16: AFI48-125 1 MARCH 1999 15 Chapter 4
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- Page 21 and 22: AFI48-125 1 MARCH 1999 21 Chapter 7
- Page 23 and 24: AFI48-125 1 MARCH 1999 23 Chapter 8
- Page 25 and 26: AFI48-125 1 MARCH 1999 25 Chapter 9
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- Page 37 and 38: AFI48-125 1 MARCH 1999 37 a tissue
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- Page 45: AFI48-125 1 MARCH 1999 45 Table A1.
40 <strong><strong>AF</strong>I</strong><strong>48</strong>-<strong>125</strong> 1 MARCH 1999<br />
result of employment in an occupation involving the use of radioactive material or equipment capable of<br />
producing ionizing radiation.<br />
overexposure (quarterly or annual)—Any accumulated or one-time ionizing radiation exposure<br />
exceeding the limits specified in 10 CFR.<br />
Permit—A written authorization to possess and use radiation sources issued by <strong>AF</strong>MOA/SGOR under<br />
the provisions of NRC Air Force Master Material License.<br />
Person—Any individual, corporation, partnership, firm, association, trust, estate, public or private<br />
institution, group, Government agency other than the NRC or the DoE subject to the licensing and related<br />
regulatory authority of the NRC and/or the Air Force Master Material License.<br />
planned special exposure (PSE)—An exposure that occurs infrequently during normal operations when<br />
it is necessary to permit a worker to receive doses in excess of the annual dose equivalent limits. Evaluate<br />
dose-limiting provisions for planned special exposures separately from and in addition to the<br />
dose-limiting conditions for normal exposure conditions. <strong>AF</strong>MOA/SGOR must approve all planned<br />
special exposures beforehand.<br />
public dose—The dose received by a member of the public from exposure to radiation and/or radioactive<br />
material released by a licensee, or to any other source of radiation under the control of the licensee. Public<br />
dose does not include occupational dose or doses received from background radiation, from any medical<br />
administration the individual has received, or from voluntary participation in medical research programs.<br />
Quality Factor (Q)—The modifying factor shown in Table A1.2. that is used to derive dose equivalent<br />
from absorbed dose.<br />
If it is more convenient to measure the neutron fluence rate than to determine the neutron dose equivalent<br />
rate in rems per hour or sieverts per hour, as provided in paragraph (b) of this section, 1 rem (0.01 Sv) of<br />
neutron radiation of unknown energies may, for purposes of the regulations in this part, be assumed to<br />
result from a total fluence of 25 million neutrons per square centimeter incident upon the body. If sufficient<br />
information exists to estimate the approximate energy distribution of the neutrons, the licensee may<br />
use the fluence rate per unit dose equivalent or the appropriate Q value from Table A1.3. to convert a<br />
measured tissue dose in rads to dose equivalent in rems.