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Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit
Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit
This paper provides insights into the neutronic similarities between a representative high-capacity rail-transport cask containing typical pressurized water reactor (PWR) spent nuclear fuel assemblies and critical reactor state-points, referred to as commercial reactor critical (CRC) state-points. Forty CRC state-points from five PWRs were analyzed, and the characteristics of CRC state-points that may be applicable for validation of burnup-credit criticality safety calculations for spent fuel transport/storage/disposal systems were identified.
Review of Results for the OECD/NEA Phase VII Benchmark: Study of Spent Fuel Compositions for Long-Term Disposal
Review of Results for the OECD/NEA Phase VII Benchmark: Study of Spent Fuel Compositions for Long-Term Disposal
OCRWM Bulletin Fall 1995
OCRWM Bulletin Fall 1995
<p>A report from the US Deparement of Energy's Office of Civilian Radioactive Waste Management</p>
<p>Regulatory Drop Tests Planned for a Model Transportation Cask</p>
<p>Implementation Plan for the environmental Impact Statement for a Multi-Purpose Canister System for Management of Civilian and Naval Spent Nuclear Fuel Issued</p>
<p>Nuclear Waste Technical Review Board (NWTRB) Update</p>
<p>The NWTRB</p>
<p>Dry Transfer System Design Under Way</p>