title: Current status of whole-body counting as a means to detect and quantify previous exposures to radioactive materials. Whole-body Counting Working Group.
abstract: This report discusses the principles, techniques, and application of whole-body counting with respect to previous radiation exposure. Whole-body counting facilities are located nationwide and have a wide range of capabilities. A listing of these facilities is provided in Appendix A. However, only a few facilities are truly state-of-the-art and have the sophisticated capabilities required to attempt detection of low-level activity in vivo. Measurements made many years after exposure can be extremely difficult to interpret. The precision and accuracy of resulting dose estimates are functions of such factors as the assumptions made concerning intake, time since intake, radionuclide metabolism, and level of intake. The indiscriminate application of metabolic models to current body contents or minimum detectable amounts of radionuclides with relatively short effective half-lives (such as 137Cs) can lead to absurd results when used as a basis for calculating intakes 25 and 40 y ago. Skull counting for 90Sr-90Y and 239,240Pu can set upper limits on possible uptakes and radiation doses, but in the case of 239,240Pu, the limits are rather high. In both cases, the accuracy of the limits depends on the metabolic models used in the calculations. These models (ICRP 1979) were developed to set safety standards for the intakes of radionuclides by workers and are not intended to be used to back-calculate uptakes and radiation doses from measurements made long after the uptake. There are, therefore, large uncertainties in any conclusions derived from these calculations. The experience gained over the years with whole- and partial-body counting has consistently shown that they are of little use in determining body contents of radionuclides resulting from exposure to weapons debris decades earlier. The development of new detectors such as an array of lithium-drifted silicon devices offers some hope of lowering the minimum detectable amount (MDA) for Pu and Am, but such detectors are still several years from routine application and do not represent current state-of-the-art. Furthermore, it is doubtful that such improvements will be sufficient to meet the need of assessing radiation exposures that occurred decades earlier.
authors.affiliation: Argonne National Laboratory, IL 60439.
authors.forename: R
authors.initials: R
authors.lastname: Toohey
authors.forename: E
authors.initials: E
authors.lastname: Palmer
authors.forename: L
authors.initials: L
authors.lastname: Anderson
authors.forename: C
authors.initials: C
authors.lastname: Berger
authors.forename: N
authors.initials: N
authors.lastname: Cohen
authors.forename: G
authors.initials: G
authors.lastname: Eisele
authors.forename: B
authors.initials: B
authors.lastname: Wachholz
authors.forename: W
authors.initials: W
authors.lastname: Burr
mesh_terms: D000059:Accidents; D006801:Humans; D009688:Nuclear Reactors; D009689:Nuclear Warfare; D016273:Occupational Exposure; D011829:Radiation Dosage; D011847:Radioactive Fallout; D014915:Whole-Body Counting / Q000295:instrumentation / Q000379:methods
chemical_list: D011847:Radioactive Fallout