Abstract
Oak Ridge National Laboratory is conducting radiochemical assay experiments, using high-precision analytical protocols validated with a comprehensive quality assurance plan, to expand the nuclide inventory validation basis for high burnup spent nuclear fuel. Preliminary measurement data for key actinides and fission products in two pressurized water reactor spent fuel samples are being used to investigate the impact of measurement data uncertainty on the sample burnup estimation. These measurement data are also being used to examine the impact of assumptions applied when developing best-estimate computational models to simulate fuel irradiation history. The simulations are being performed using depletion capabilities in the SCALE code system. Comparison of calculated and measured nuclide concentrations shows good agreement for the considered nuclides.
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 | 874-883 |
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 funded by the US Nuclear Regulatory Commission (NRC) and the US Department of Energy (OD E). The authors would like to thank Don Algama of the NRC Office of Nuclear Regulatory Research for his continued support and valuable feedback.
Keywords
- SCALE
- nuclide inventory
- radiochemical assay
- spent nuclear fuel
- validation