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Neutron/gamma dose characterization for use with TLD

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:7015876
The work described in this paper was performed in preparation for establishing a thermoluminescent dosimetry (TLD) system for workers exposed to spontaneous fission neutrons from mixed plutonium isotopes, {sup 232}Th, and depleted uranium at the US Department of Energy (DOE) Pantex facility. The method proposed uses a neutron-insensitive thermoluminescent dosimeter to measure the gamma dose and apply a neutron dose/gamma dose ratio to calculate the neutron dose equivalent. This approach, while requiring multibadge dosimetry for each individual, provides a more accurate neutron dose calculation than was previously in use and reduces the maximum missed dose and falsely reported dose.
OSTI ID:
7015876
Report Number(s):
CONF-911107--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 63
Country of Publication:
United States
Language:
English