Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit

I. C. Gauld; U. Mertyurek

doi:10.1016/j.nucengdes.2019.01.026

Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit

I. C. Gauld
, U. Mertyurek

Research output: Contribution to journal › Article › peer-review

32 Scopus citations

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.

Original language	English
Pages (from-to)	110-124
Number of pages	15
Journal	Nuclear Engineering and Design
Volume	345
DOIs	https://doi.org/10.1016/j.nucengdes.2019.01.026
State	Published - Apr 15 2019

Funding

This work was supported by the US Nuclear Regulatory Commission Office of Nuclear Regulatory Research and DOE Office of Nuclear Energy Spent Fuel and Waste Disposition Program. The significant contributions of the Japan Atomic Energy Agency and the Japan Nuclear Regulation Authority to make BWR assay measurement data available to the international community are gratefully acknowledged. This paper is dedicated to the memory of Stephen Bowman ( 1956-2018 ), SCALE project leader from 1995-2009 , and manager of the BWR burnup credit project, for his leadership, guidance, and friendship. This work was supported by the US Nuclear Regulatory Commission Office of Nuclear Regulatory Research and DOE Office of Nuclear Energy Spent Fuel and Waste Disposition Program. The significant contributions of the Japan Atomic Energy Agency and the Japan Nuclear Regulation Authority to make BWR assay measurement data available to the international community are gratefully acknowledged. This paper is dedicated to the memory of Stephen Bowman (1956-2018), SCALE project leader from 1995-2009, and manager of the BWR burnup credit project, for his leadership, guidance, and friendship.

Keywords

Boiling water reactor
Burnup credit
Isotopic validation
Radiochemical assay data

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10.1016/j.nucengdes.2019.01.026

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title = "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.",

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author = "Gauld, \{I. C.\} and U. Mertyurek",

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AU - Mertyurek, U.

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N2 - 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.

AB - 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.

KW - Boiling water reactor

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KW - Radiochemical assay data

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JO - Nuclear Engineering and Design

JF - Nuclear Engineering and Design

ER -

Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit

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Keywords

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