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Denver, CO|Sheraton Denver
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Oak Ridge focuses neutron scattering studies on TRISO fuels
Oak Ridge National Laboratory is reporting a development in TRISO fuel research that could help evaluate high-temperature gas reactor fuels. ORNL researchers used the Spallation Neutrons and Pressure Diffractometer at the lab’s Spallation Neutron Source to make neutron scattering measurements on TRISO fuel particles containing high-assay low-enriched uranium (HALEU).
Technical Session|Panel|Sponsored by FCWMD
Monday, November 16, 2020|1:00–3:10PM EST
Session Chair:
Kaushik Banerjee
Session Organizer:
Alternate Chair:
Christina Leggett
Staff Producer:
Eileen Cullen (American Nuclear Society)
Spent nuclear fuel (SNF) cask systems are evaluated for approved contents that provide bounding fuel characteristics (design-basis) such as fuel type, initial enrichment, and discharge burnup. The bounding fuel characteristics establish the upper limits of the cask's safety parameters (e.g., dose rates). Due to the wide variation in SNF assembly burnup values and discharge dates, cask systems are loaded with assemblies that satisfy the bounding fuel characteristics with some amount of uncredited safety margin. In this session, we will discuss (1) design-basis and as-loaded analysis approaches and (2) various applications of uncredited safety margins that can be quantified by as-loaded analyses. The as-loaded analysis approach has the potential to significantly improve SNF management and streamline the regulatory review process.
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