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DOSE COEFFICIENTS FOR INTAKES OF RADIONUCLIDES VIA CONTAMINATED WOUNDS

Toohey, R. E.*; Bertelli, L.; Sugarman, S. L.*; Wiley, A. L.*; Christensen, D. M.*

doi: 10.1097/HP.0b013e3181fb2e01
Paper

The NCRP Wound Model, which describes the retention of selected radionuclides at the site of a contaminated wound and their uptake into the transfer compartment, has been combined with the ICRP element-specific systemic models for those radionuclides to derive dose coefficients for intakes via contaminated wounds. These coefficients can be used to generate derived regulatory guidance (i.e., the activity in a wound that would result in an effective dose of 20 or 50 mSv, or in some cases, a organ-equivalent dose of 500 mSv) and clinical decision guidance (i.e., activity levels that would indicate the need for consideration of medical intervention to remove activity from the wound site, administration of decorporation therapy or both). Data are provided for 38 radionuclides commonly encountered in various activities such as nuclear weapons, fuel fabrication or recycling, waste disposal, medicine, research, and nuclear power. These include 3H, 14C, 32P, 35S, 59Fe, 57,58,60Co, 85,89,90Sr, 99mTc, 106Ru, 125,129,131I, 134,137Cs, 192Ir, 201Tl, 210Po, 226,228Ra, 228,230,232Th, 234,235,238U, 237Np, 238,239,240,241Pu, 241Am, 242,244Cm, and 252Cf.

* Radiation Emergency Assistance Center/Training Site, Oak Ridge Institute for Science and Education, Oak Ridge, TN 37031-0117; Radiation Protection Division, Los Alamos National Laboratory, Los Alamos, NM 87545.

For correspondence contact: R. E. Toohey, ORAU, P.O. Box 117, MS 19, Oak Ridge, TN 37830-0117, or email at dick.toohey@orau.org.

(Manuscript accepted 6 September 2010)

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