Radiation whole body

Whole body monitoring. Whole body monitoring is the preferred method of dose assessment for radionuclides that emit penetrating radiation. Whole body counters are used to measure the activity of radioactive material deposited in different parts of the body. From the measured activity, the intake of the person and the resulting internal dose can be calculated using models. Whole body counting should be performed periodically. 

Most physicians do not test for americium in their offices, but they can collect samples and send them to special laboratories. Since americium is radioactive, it is normally measured by its radiation emissions. These emissions are used to tell the amount of americium (in curies or Becquerels) and the radiation dose it gives to your body (in Sieverts or rem). Radiation detectors measure the radiation that is released from objects or materials, including the whole body. If... 

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. 

Epidemiological and Human Dosimetry Studies. Epidemiological studies of radiation dose typically involve estimates of exposure that are based on whole-body measurements of internally-deposited americium. A need remains for epidemiological data that can provide quantitative human dose-response information while supplying additional information on the health effects of exposure to ionizing radiation and americium in particular, for cases of known internal exposure. 

During refueling, the respective concentrations were 1.64, 1.33, 0.78, 0.19, and 6.34 mBq/m3 (44.3, 35.9, 21,5.1, and 171 fCi/m3). The derived air concentration recommended by the ICRP for occupational exposure is 80.0 mBq/m3 (2,200 fCi/m3). In 1997, the French radiation protection office conducted monitoring (24-hour urine analysis/whole body activity measurements) of workers in the non-nuclear energy field (i.e., nuclear medicine, research laboratories, and non-nuclear industries) to ascertain the occupational intake of radionuclides (De Vathaire et al. 1998). 241Am was not detected in samples from any of the 37 workers who worked with the isotope. 

Badjin VI, Molokanov AA. 1998. Application of the recent ICRP models for estimating the intake of 241Pu from 241 Am whole-body counter measurements. Radiat Prot Dosim 79(1-4) 141-144. 

McInroy JF, Kathren RL, Swint MJ. 1989. Distribution of plutonium and americium in whole bodies donated to the United States Transuranium Registry. Radiat Prot Dosim 26(1/4) 151-158. 

Annual whole-body radiation doses to humans from various sources... 

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

Table 32.5 Annual Whole-Body Radiation Doses to Humans from Various Sources... 

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... 

Benjamin, S.A., G.M. Angleton, A.C. Lee, WJ. Saunders, and J.S. Williams. 1990. Health effects from whole-body irradiation during development in beagles studies at Colorado State University. Radiation Res. 124 366-368. 

Fry, R.J.M. 1991. Radiation carcinogenesis in the whole-body system. Radiation Res. 126 157-161. 

In radiation protection studies, it was found that orotic acid does not offer a protective effect in mice against the whole-body X-irradiation of 700 y or 550 7 [189]. On the other hand, orotic acid, alone or with folic acid, definitely increased the survival rate of irradiated rats and guinea-pigs by 20—30 per cent, while hemopoiesis was not affected [190]. 

Cisplatin was first characterized as a radiation sensitizer using hypoxic Bacillus megaterium spores (53). Radiation sensitization by cisplatin was confirmed in vegetative Escherichia coli with a maximum sensitizer enhancement ratio of 1.77 in anoxic bacteria at a cisplatin concentration of 50 uM (54). Zimbrick et al. (55) extended these studies to other platinum complexes. The earliest studies in mammalian cells used hypoxic V-79 Chinese hamster cells and showed a small radiation sensitization with 8 iM of cisplatin (56). Nias and Szumiel (57) first reported that pretreatment of Chinese hamster ovary (CHO) cells with a platinum complex could sensitize well-oxygenated cells to radiation. Wodinsky etal. (58) showed that cisplatin potentiated the effect of whole-body radiation therapy in mice inoculated intraperitoneally with P388 leukemia compared with either modality alone. Therapeutic potentiation was found in MTG-B subcutaneous tumors and intracerebral RBT when the animals were treated with cisplatin and radiation (59). 

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. 

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