Category of Content
Siting Experience Documents Only
Publication Date
Keywords
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 Winter 1995
OCRWM Bulletin Winter 1995
<p>A newsletter from the Office of Civilian Radioactive Waste Management</p>
<p>OCRWM Director Briefs US. Nuclear Regulatory Commission .</p>
<p>Notice of Inquiry: Technical Assistance and Training for Safe Transportation of Radioactive Waste</p>
<p>OCRWM Program Plan</p>
<p>Environmental Impact Statement Scoping for the Multi-Purpose Canister-Based System</p>
<p>Nuclear Waste Technical Review Board Update,</p>
<p>Nuclear Wasre Negotiator Update</p>