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Title: Dose Rate Analysis Capability for Actual Spent Fuel Transportation Cask Contents

The approved contents for a U.S. Nuclear Regulatory Commission (NRC) licensed spent nuclear fuel casks are typically based on bounding used nuclear fuel (UNF) characteristics. However, the contents of the UNF canisters currently in storage at independent spent fuel storage installations are considerably heterogeneous in terms of fuel assembly burnup, initial enrichment, decay time, cladding integrity, etc. Used Nuclear Fuel Storage, Transportation & Disposal Analysis Resource and Data System (UNF ST&DARDS) is an integrated data and analysis system that facilitates automated cask-specific safety analyses based on actual characteristics of the as-loaded UNF. The UNF-ST&DARDS analysis capabilities have been recently expanded to include dose rate analysis of as-loaded transportation packages. Realistic dose rate values based on actual canister contents may be used in place of bounding dose rate values to support development of repackaging operations procedures, evaluation of radiation-related transportation risks, and communication with stakeholders. This paper describes the UNF-ST&DARDS dose rate analysis methodology based on actual UNF canister contents and presents sample dose rate calculation results.
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  1. ORNL
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OSTI Identifier:
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Resource Relation:
Conference: Institute of Nuclear Materials Management (INMM) - 55th Annual Meeting, Atlanta, GA, USA, 20140720, 20140724
Research Org:
Oak Ridge National Laboratory (ORNL)
Sponsoring Org:
NE USDOE - Office of Nuclear Energy
Country of Publication:
United States