Open AccessCriticality safety evaluation report for the multi-canister overpack
Author(s) -
S.F. Kessler
Publication year - 1999
Language(s) - English
Resource type - Reports
DOI - 10.2172/782361
Subject(s) - criticality , scrap , nuclear engineering , spent nuclear fuel , spent fuel pool , waste management , engineering , environmental science , mechanical engineering , physics , nuclear physics
This criticality evaluation is for Spent N Reactor fuel unloaded from the existing canisters in both KE and KW Basins, and loaded into multiple canister overpack (MCO) containers with specially built baskets containing a maximum of either 54 Mark 1V or 48 Mark IA fuel assemblies. The criticality evaluations include loading baskets into the cask-MCO, operations at the Cold Vacuum Drying Facility, and storage in the Canister Storage Building. Many conservatisms have been built into this analysis, the primary one being the selection of the k{sub eff} = 0.95 criticality safety limit. Additional analyses in this revision include partial fuel basket loadings, loading 26.1 inch Mark IA fuel assemblies into Mark IV fuel baskets, and the revised fuel and scrap basket designs. The MCO MCNP model was revised to include the shield plug assembly