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Dose Rate Calucaltion for the DHL W/DOE SNF Codisposal Waste Package
Author(s) -
Gabriel Rădulescu
Publication year - 2000
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/893825
Subject(s) - triga , environmental science , radioactive waste , waste management , spent nuclear fuel , nuclear engineering , research reactor , nuclear physics , engineering , physics , neutron
The purpose of this calculation is to determine the surface dose rates of the short codisposal waste package (WP) of defense high-level waste (DHLW) and TRIGA (Training, Research, Isotopes, General Atomics) spent nuclear fuel (SNF). The WP contains the TRIGA SNF, in a standardized 18-in. DOE (U.S. Department of Energy) SNF canister, and five 3-m-long Savannah River Site (SRS) DHLW pour glass canisters, which surround the DOE SNF canister

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