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 Spring 1995
OCRWM Bulletin Spring 1995
<p>A newsletter from the Office of Civilian Radioactive Waste Management</p>
<p>Highlights Include....</p>
<p>OCRWM FY 1996 Budget Presented to Congress</p>
<p>Public Responds to Waste Acceptance Issues</p>
<p>Transportation External Coordination Working Group Convenes in North Carolina</p>
<p>OCRWM Completes Draft Public Participation Plan</p>
<p>International Program Update</p>