External exposure model for various geometries of contaminated materials
- Argonne National Laboratory, IL (United States)
A computational model for external exposure was developed for the U.S. Department of Energy`s residual radioactive material guideline computer code (RESRAD) on the basis of dose coefficients from Federal Guidance Report No. 12 and the point-kernel method. This model includes the effects of different materials and exposure distances, as well as source geometry (cover thickness, source depth, area, and shape). A material factor is calculated on the basis of the point-kernel method using material-specific photon cross-section data and buildup factors. This present model was incorporated into RESRAD-RECYCLE (a RESRAD family code used for computing radiological impacts of metal recycling) and is being incorporated into RESRAD-BUILD (a DOE recommended code for computing impacts of building decontamination). The model was compared with calculations performed with the Monte Carlo N-Particle Code (MCNP) and the Microshield code for three different source geometries, three different radionuclides ({sup 234}U, {sup 238}U, and {sup 60}Co, representing low, medium, and high energy, respectively), and five different source materials (iron, copper, aluminum, water, and soil). The comparison shows that results of this model are in very good agreement with MCNP calculations (within 5% for {sup 60}Co and within 30% for {sup 238}U and {sup 234}U for all materials and source geometries). Significant differences (greater than 100%) were observed with Microshield for thin {sup 234}U sources.
- OSTI ID:
- 393964
- Report Number(s):
- CONF-9607135--
- Journal Information:
- Health Physics, Journal Name: Health Physics Journal Issue: Suppl.6 Vol. 70; ISSN HLTPAO; ISSN 0017-9078
- Country of Publication:
- United States
- Language:
- English
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