Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit
Abstract
Validating boiling water reactor (BWR) spent nuclear fuel inventory calculations is challenging due to the complexity of BWR assembly designs, the lack of publicly available radiochemical assay measurements, and limited access to documentation on fuel design and operating conditions. This study compiled and evaluated experimental data on measured nuclide concentrations in commercial spent fuel for 77 fuel samples that cover a wide range of modern assembly designs and operating conditions. These data were used to validate predictions of the isotopic content using the SCALE Polaris lattice physics depletion code. The isotopic bias and uncertainties derived from comparisons of calculated and measured nuclide concentrations are applied to estimate the combined effect on the effective neutron multiplication factor for a representative burnup credit spent nuclear fuel storage system. The experimental data, validation results, model uncertainties, and uncertainty analysis results for a cask burnup credit application system are described.
- Authors:
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1547738
- Alternate Identifier(s):
- OSTI ID: 1505325
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Published Article
- Journal Name:
- Nuclear Engineering and Design
- Additional Journal Information:
- Journal Name: Nuclear Engineering and Design Journal Volume: 345 Journal Issue: C; Journal ID: ISSN 0029-5493
- Publisher:
- Elsevier
- Country of Publication:
- Netherlands
- Language:
- English
- Subject:
- 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; Boiling water reactor; Radiochemical assay data; Isotopic validation; Burnup credit
Citation Formats
Gauld, I. C., and Mertyurek, U. Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit. Netherlands: N. p., 2019.
Web. doi:10.1016/j.nucengdes.2019.01.026.
Gauld, I. C., & Mertyurek, U. Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit. Netherlands. https://doi.org/10.1016/j.nucengdes.2019.01.026
Gauld, I. C., and Mertyurek, U. Mon .
"Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit". Netherlands. https://doi.org/10.1016/j.nucengdes.2019.01.026.
@article{osti_1547738,
title = {Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit},
author = {Gauld, I. C. and Mertyurek, U.},
abstractNote = {Validating boiling water reactor (BWR) spent nuclear fuel inventory calculations is challenging due to the complexity of BWR assembly designs, the lack of publicly available radiochemical assay measurements, and limited access to documentation on fuel design and operating conditions. This study compiled and evaluated experimental data on measured nuclide concentrations in commercial spent fuel for 77 fuel samples that cover a wide range of modern assembly designs and operating conditions. These data were used to validate predictions of the isotopic content using the SCALE Polaris lattice physics depletion code. The isotopic bias and uncertainties derived from comparisons of calculated and measured nuclide concentrations are applied to estimate the combined effect on the effective neutron multiplication factor for a representative burnup credit spent nuclear fuel storage system. The experimental data, validation results, model uncertainties, and uncertainty analysis results for a cask burnup credit application system are described.},
doi = {10.1016/j.nucengdes.2019.01.026},
journal = {Nuclear Engineering and Design},
number = C,
volume = 345,
place = {Netherlands},
year = {Mon Apr 01 00:00:00 EDT 2019},
month = {Mon Apr 01 00:00:00 EDT 2019}
}
https://doi.org/10.1016/j.nucengdes.2019.01.026
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