Open AccessNAC-1 cask dose rate calculations for LWR spent fuel
Author(s) -
A.B. Carlson
Publication year - 1999
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/781543
Subject(s) - cask , spent nuclear fuel , interim , nuclear engineering , environmental science , waste management , engineering , archaeology , history
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
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