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Title: NAC-1 cask dose rate calculations for LWR spent fuel

A Nuclear Assurance Corporation nuclear fuel transport cask, NAC-1, is being considered as a transport and storage option for spent nuclear fuel located in the B-Cell of the 324 Building. The loaded casks will be shipped to the 200 East Area Interim Storage Area for dry interim storage. Several calculations were performed to assess the photon and neutron dose rates. This report describes the analytical methods, models, and results of this investigation.
Authors:
Publication Date:
OSTI Identifier:
781543
Report Number(s):
HNF-3016-REV0; EW7040000
EW7040000; TRN: US0111165
DOE Contract Number:
AC06-96RL13200
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 24 Feb 1999
Research Org:
HNF Hanford Site (US)
Sponsoring Org:
US DOE Office of Environmental Management (US)
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; SPENT FUEL CASKS; DOSE RATES; NEUTRONS; PHOTONS; SPENT FUELS; DRY STORAGE; TRANSPORT; CALCULATION METHODS; MATHEMATICAL MODELS