skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Criticality Safety Evaluation Report CSER-96-019 for Spent Nuclear Fuel (SNF) Processing and Storage Facilities Multi Canister Overpack (MCO)

Abstract

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 IV or 48 Mark IA fuel assemblies. The criticality evaluations include loading baskets into the cask-MCO, operation at the Cold Vacuum Drying Facility,a nd 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. This revision incorporates the analyses for the sampling/weld station in the Canister Storage Building and additional analysis of the MCO during the draining at CVDF. Additional discussion of the scrap basket model was added to show why the addition of copper divider plates was not included in the models.

Authors:
Publication Date:
Research Org.:
FDNW (US)
Sponsoring Org.:
ENVIRONMENTAL MANAGEMENT (US)
OSTI Identifier:
798146
Report Number(s):
HNF-SD-SNF-CSER-005, Rev.5
ECN-647522; TRN: US0205254
DOE Contract Number:  
AC06-96RL13200
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 20 Oct 1999
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; CONTAINERS; COPPER; CRITICALITY; DRYING; EVALUATION; FUEL ASSEMBLIES; N-REACTOR; NUCLEAR FUELS; SAFETY; STORAGE; STORAGE FACILITIES

Citation Formats

KESSLER, S F. Criticality Safety Evaluation Report CSER-96-019 for Spent Nuclear Fuel (SNF) Processing and Storage Facilities Multi Canister Overpack (MCO). United States: N. p., 1999. Web. doi:10.2172/798146.
KESSLER, S F. Criticality Safety Evaluation Report CSER-96-019 for Spent Nuclear Fuel (SNF) Processing and Storage Facilities Multi Canister Overpack (MCO). United States. doi:10.2172/798146.
KESSLER, S F. Wed . "Criticality Safety Evaluation Report CSER-96-019 for Spent Nuclear Fuel (SNF) Processing and Storage Facilities Multi Canister Overpack (MCO)". United States. doi:10.2172/798146. https://www.osti.gov/servlets/purl/798146.
@article{osti_798146,
title = {Criticality Safety Evaluation Report CSER-96-019 for Spent Nuclear Fuel (SNF) Processing and Storage Facilities Multi Canister Overpack (MCO)},
author = {KESSLER, S F},
abstractNote = {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 IV or 48 Mark IA fuel assemblies. The criticality evaluations include loading baskets into the cask-MCO, operation at the Cold Vacuum Drying Facility,a nd 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. This revision incorporates the analyses for the sampling/weld station in the Canister Storage Building and additional analysis of the MCO during the draining at CVDF. Additional discussion of the scrap basket model was added to show why the addition of copper divider plates was not included in the models.},
doi = {10.2172/798146},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1999},
month = {10}
}