Abstract
The development of accident-tolerant fuel and advanced reactors fueled with high-assay low-enriched uranium has created an increased focus on systems with uranium enrichments between 5 and 20 wt % 235U. SCALE criticality safety validation reports generated at Oak Ridge National Laboratory contain very few benchmark experiments in this range. The work presented herein is an initial investigation of expanded validation of the entire range of enrichments for uranium-fueled systems, including consideration of over 300 newly developed KENO models. The vast majority of the new models are between 4.4 wt % and 37.5 wt % enrichment and include a variety of thermal, intermediate, and mixed neutron spectra. This work finds no strong evidence of an enrichment-dependent bias, but there are indications of a spectrum-dependent bias. There are, however, only a limited number of independent experiments included at this time to distinguish intermediate enrichment effects from intermediate spectrum effects. Further work in this area is ongoing for intermediate enrichment systems. In the long run, the addition of these models to the Verified, Archived Library and Inputs and Data is planned, as funding and staff availability allow.
Original language | English |
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Title of host publication | Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022 |
Publisher | American Nuclear Society |
Pages | 2664-2673 |
Number of pages | 10 |
ISBN (Electronic) | 9780894487873 |
DOIs | |
State | Published - 2022 |
Event | 2022 International Conference on Physics of Reactors, PHYSOR 2022 - Pittsburgh, United States Duration: May 15 2022 → May 20 2022 |
Publication series
Name | Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022 |
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Conference
Conference | 2022 International Conference on Physics of Reactors, PHYSOR 2022 |
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Country/Territory | United States |
City | Pittsburgh |
Period | 05/15/22 → 05/20/22 |
Funding
This work was supported by the Nuclear Criticality Safety Program, funded and managed by the National Nuclear Security Administration for the Department of Energy. Additional support has been provided by the US Nuclear Regulatory Commission office of Nuclear Regulatory Research. This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan). This work was supported by the Nuclear Criticality Safety Program, funded and managed by the National Nuclear Security Administration for the Department of Energy. Additional support has been provided by the US Nuclear Regulatory Commission office of Nuclear Regulatory Research. ∗ Notice: This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan).
Keywords
- HALEU
- LEU+
- SCALE
- criticality safety
- validation