Nuclide Inventory Benchmark for BWR Spent Nuclear Fuel: Challenges in Evaluation of Modeling Data Assumptions and Uncertainties

Journal Article · 30 January 2022 · Journal of Nuclear Engineering

DOI: https://doi.org/10.3390/jne3010003 · OSTI ID:1843695

Mertyurek, Ugur  ^[1]; Ilas, Germina ^[1]

---

1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

This work discusses challenges and approaches to uncertainty analyses associated with the development of a nuclide inventory benchmark for fuel irradiated in a boiling water reactor. The benchmark under consideration is being developed based on experimental data from the SFCOMPO international database. The focus herein is on how to address missing data in fuel design and operating conditions that are important for adequately simulating the time-dependent changes in fuel during irradiation in the reactor. The effects of modeling assumptions and uncertainties in modeling parameters on the calculated nuclide inventory were analyzed and quantified through computational models developed using capabilities in the SCALE code system. Particular attention was given to the impact of the power history and water coolant density on the calculated nuclide inventory, as well as to the effect of geometry modeling considerations not usually addressed in a nuclide inventory benchmark. These considerations include gap closure, channel bow, and channel corner radius, which do not usually apply to regular reactor operation but are relevant for assessing impacts of potential anomalous operating scenarios.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Science (SC)
• Grant/Contract Number: AC05-00OR22725
• OSTI ID: 1843695
• Journal Information: Journal of Nuclear Engineering, Journal Name: Journal of Nuclear Engineering Journal Issue: 1 Vol. 3; ISSN 2673-4362
• Publisher: MDPICopyright Statement
• Country of Publication: United States
• Language: English