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Annual limits on intake

The model was developed to predict skeletal and soft tissue burdens of americium in people who may be exposed to americium. Comparisons of annual limits on intake derived from the model and the ICRP (1979) model are presented. Descriptions of applications of the model in risk assessment have not been reported. [Pg.104]

The NRC requires that the occupational intake of americium isotopes not exceed certain specified Annual Limits on Intake (ALIs) for the inhalation and oral routes of exposure. For241 Am and 243Am, the oral ingestion ALI is 0.8 JLlCi and the inhalation ALI is 0.006 pCi, both of which are based on the deterministic dose limit to the bone surface (NRC 2000). [Pg.203]

Stradling GN, Stather JW. 1989. The use of animal experiments for assessing annual limits on intake and interpreting chest-monitoring data for workers exposed to industrial actinide-bearing dusts. Health Phys 37(Suppl. l) 221-228. [Pg.262]

International Commission on Radiological Protection (ICRP). 1991b. Annual limits on intake of radionuclides by workers based on the 1990 recommendations. ICRP Publ. 61. Ann. ICRP 21(4) 1-41. [Pg.1743]

DOE. 1996c. Annual limits on intake (ALIs) and derived air concentrations (DACs) of radionuclides for occupational exposure effluent concentrations concentrations for release to sewerage. 10CFR20 Appendix B. U. S. Department of Energy, Washington, D.C. [Pg.357]

The SITP is a quantity derived from the Annual Limit on Intake (ALI), an internationally accepted concept that has been acknowledged by the Government s Radioactive Waste Management Committee (RWMAC) as a valid method of establishing equivalent hazards of different waste types. The ALI is a derived limit for the permissible amount of radioactive material taken into the body of an adult radiation worker by inhalation or ingestion in a year. The ALI is the smaller value of intake of a given radionuclide in a year by the reference man that would result in either a committed effective dose equivalent of 0.05 Sv or 0.5 Sv to any individual organ or tissue. [Pg.129]

Bronchopulmonary lavage may also be effective for removal of inhaled plutonium, and has been recommended for occupational intakes of insoluble forms exceeding 100 times the annual limit on intake. [Pg.2036]

Annual limit on intake (occupational exposure) for inhalation of selected Pu isotopes ... [Pg.2036]

Effective Dose Coefficients (e(50)) and Annual Limits on Intake (ALI) for Occupational... [Pg.16]

ACGIH = American Conference of Governmental Industrial Hygienists ADEC = Alaska Department of Environmental Conservation ALI = annual limits on intake BNA = Bureau of National Affairs CFR = Code of Federal Regulations DAC = derived air concentration DEP = Department of Environmental Protection DOE = Department of Energy DOT = Department of Transportation EPA = Environmental Protection Agency ... [Pg.313]

ALI = Annual Limits on Intake AMAD = Activity Median Average Diameters Bq = Bequerels Ci = Curies d = day hr... [Pg.315]

The occupational exposure values for the inhalation of uranium have been compiled by the American Conference of Governmental Industrial Hygienists (ACGIH) [14]. These are air concentration exposure limits based on the chemical effects of uranium. In contrast, the International Commission on Radiological Protection (ICRP) has developed the annual limit on intake (ALI) for ingestion and inhalation of uranium compounds based solely on the radiation doses received by tissues and organs of the body [12,15]. Whether the primary concern is the chemical toxicity or radiation dose, the occupational limits take the solubility of the uranium compound into consideration. The occupational limits are summarized in Table 3. It must be emphasized that the air concentration exposure limits are for the typical 8-hr day (see Abbrevi-... [Pg.642]

The Interoatioital Corttrttission on Radiological Protection, Annual Limits on Intake iff Radionuclides by Workers Based on the 1990 Recommendations, ICRP Publ. 61, Pergairton Press, Oxford, 1991. [Pg.648]

The key characteristics that need to be known about any radioactive material to plan the appropriate radiation protection measures are principal emissions and their energies half-life annual limit on intake (ALI) shielding requirement [e.g., halfvalue layer (HVL)] monitoring requirements and special considerations (e.g., physi-... [Pg.471]

Radionuclide Half-life Maximum beta energy (MeV) Principal X or gamma energy (MeV) Annual limit on intake (Bq) by inhlalation ... [Pg.472]

In accordance with 10 CFR 20, the Annual Limit on Intake (ALI) refers to ... [Pg.416]


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