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Body dose

The Leggett (1992) model was developed to predict tissue doses and whole-body dose to people who may be exposed to americium. The model is considered an updated version of the ICRP (1989) model for americium, which has been used to establish risk-based limits of intake of241 Am (ICRP 1989). The Leggett (1992) and ICRP (1989) models predict similar long-term average doses of americium to the liver and skeleton for an injection exposure and would be expected to predict similar radiation risks and risk-based intake limits (Leggett 1992). Descriptions of applications of the Leggett (1992) model in risk assessment have not been reported. [Pg.97]

The USTUR (1994) model was developed to predict tissue doses and whole-body dose to people who may be exposed to americium. The model has been used to calculate Annual Limits of Intake (ALIs) for 241Am, and yielded similar, but lower limits than those estimated using the ICRP model (1989). [Pg.98]

Both the general population and workers may be exposed to 241 Am from the production, distribution, and use of ionization chamber smoke detectors. The NRC investigated exposure relating to this device. Their 1979 report concluded that the sum of doses to the population resulting from production, distribution, use, and disposal of 14 million smoke detectors containing 3 pCi (100 kBq) of 241Am each (over 3 times that presently used) that were distributed in 1978 would result in a collective total body dose of 1,100 person-rem (11 person-Sv)—much lower than that which could potentially result in one cancer death (NRC 1979). Exposure to 241Am could result from improper disposal of smoke detectors. The detector could be broken and then disposed of in a municipal landfill or incinerated. The 241 Am from the broken detector could be consumed by a child. [Pg.190]

Survival time and associated mode of death of selected mammals after whole-body doses of gamma radiation... [Pg.32]

Figure 32.9 Survival time and associated mode of death of selected mammals after whole-body doses of gamma radiation. (Modified from Hobbs, C.H. and R.O. McClellan. 1986. Toxic effects of radiation and radioactive materials. Pages 669-705 in C.D. Klaassen, M.O. Amdur, and J. Doull [eds.]. Casarett and Doull s Toxicology. Third Edition. Macmillan, New York United Nations Scientific Committee on the Effects of Atomic Radiation [UNSCEAR]. 1988. Sources, Effects and Risks of Ionizing Radiation. United Nations, New York. 647 pp.)... Figure 32.9 Survival time and associated mode of death of selected mammals after whole-body doses of gamma radiation. (Modified from Hobbs, C.H. and R.O. McClellan. 1986. Toxic effects of radiation and radioactive materials. Pages 669-705 in C.D. Klaassen, M.O. Amdur, and J. Doull [eds.]. Casarett and Doull s Toxicology. Third Edition. Macmillan, New York United Nations Scientific Committee on the Effects of Atomic Radiation [UNSCEAR]. 1988. Sources, Effects and Risks of Ionizing Radiation. United Nations, New York. 647 pp.)...
Total beta and gamma radiation Total annual whole-body dose equivalent, or dose 3... [Pg.1732]

Individual - operational guide for "suitable sample of population when Individual whole body doses are not known... [Pg.127]

B.5.3 Effective Dose Equivalent and Effective Dose Equivalent Rate. The absorbed dose is usually defined as the mean absorbed dose within an organ or tissue. This represents a simplification of the actual problem. Normally when an individual ingests or inhales a radionuclide or is exposed to external radiation that enters the body (gamma), the dose is not uniform throughout the whole body. The simplifying assumption is that the detriment will be the same whether the body is uniformly or nonuniformly irradiated. In an attempt to compare detriment from absorbed dose of a limited portion of the body with the detriment from total body dose, the ICRP (1977) has derived a concept of effective dose equivalent. [Pg.173]

Total annual whole-body dose equivalent, or dose to any internal organ, <0.04 mSv (<0.004 rem), based on individual consumption of 2 L daily of drinking water from a groundwater source... [Pg.1778]

These bodies dosely lesemble the oonesponding sulphtir compounds. [Pg.85]

In our work with characterizing PAH in the work environment, we have felt that it is necessary to establish body doses through appropriate body fluid analysis for a better risk evaluation of occupational exposure. Analysis of metabolites and adducts between cellular macromolecules and -metabolites is in progress. [Pg.375]

Integrated total body dose for a 50-yr Malaga man —HLW + LLW. Maximum measured permeability used in the transport calculation. Event initiation at 1,000 yr after sealing. [Pg.24]

K is a (3 -emitting nuclide that is the predominant radioactive component of normal foods and human tissue. Due to the 1460-keV 7 ray that accompanies the (3 decay, it is also an important source of background radiation detected by 7-ray spectrometers. The natural concentration in the body contributes about 17 mrem/y to the whole body dose. The specific activity of 40K is approximately 855 pCi/g potassium. Despite the high specific activity of 87Rb of 2400 pCi/g, the low abundance of rubidium in nature makes its contribution to the overall radioactivity of the environment small. [Pg.78]

Methadone is given orally (different from the usual means of abuse), and thereby also substitutes for the paraphernalia that accompany illicit drug use. Methadone helps relieve the craving for more drug and delays the appearance of withdrawal symptoms as long as it is in the body. Doses are gradually decreased. If the dose of morphine that was abused is known, then 1 mg of methadone can substitute for 4 mg of morphine. Otherwise, a dose of 10-50 mg a day is generally used, and can be reduced by 20% per day. [Pg.360]

When gross beta particle activity exceeds 50 pCi L radioactive constituents must be identified total body doses must be calculated. [Pg.492]


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See also in sourсe #XX -- [ Pg.737 ]




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Dose from a Photon Source Inside the Body

Dose from a Source of Charged Particles Inside the Body

Whole-body dose

Whole-body dose 462 Subject

Whole-body dose irradiation

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