Comparison of calculated and measured spent nuclear fuel decay heat with CASMO5, SNF and standard methods

D. Rochman; J. Taforeau; T. Simeonov; A. Shama

doi:10.1016/j.nucengdes.2023.112392

Comparison of calculated and measured spent nuclear fuel decay heat with CASMO5, SNF and standard methods

D. Rochman
, J. Taforeau
, T. Simeonov
, A. Shama

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

2 Scopus citations

Abstract

In this paper, we present a comparison between measured and calculated decay values for spent nuclear fuel assemblies from the Clab, GE-Morris EMAD facilities. Two codes are applied: CASMO5 and SNF, using different nuclear data libraries (JEF-2.2, JEFF-3.1.1, JEFF-3.2, ENDF/B-VII.1 and ENDF/B-VIII.0) and different code versions. Additionally values from four standard and guides for calculation of decay heats (ANS 2014, DIN 2014, ISO 2022 and RG-3.54 2018) were also compared with the measurements. All simulations with different codes, code versions and methods are based on the same geometry and irradiation descriptions for a single assembly, providing more convenient comparisons of results. The impact of nuclear data libraries and computational methods are shown, compared to the spread of C/E (Calculations over Experiment) values between the 256 considered measurements. Finally, a comparison of the most important nuclides contributing to the decay heat is presented between measured assemblies and more recent cases corresponding to higher burnup, initial enrichment and longer cooling times.

Original language	English
Article number	112392
Journal	Nuclear Engineering and Design
Volume	410
DOIs	https://doi.org/10.1016/j.nucengdes.2023.112392
State	Published - Aug 15 2023
Externally published	Yes

Funding

One of the authors (D. Rochman) acknowledges that part of this work was partly supported by swissnuclear, the association of the Swiss nuclear power station operators, with the COLOSS-2 project. It was also partly funded by the European Union's Horizon 2020 Research and Innovation Programme under grant agreement No 847593 (project EURAD, Work Package 8). All authors listed have made a substantial, direct, and intellectual contribution to the work and approved it for publication. One of the authors (D. Rochman) acknowledges that part of this work was partly supported by swissnuclear , the association of the Swiss nuclear power station operators , with the COLOSS-2 project.

Keywords

Neutronics
Spent nuclear fuel
Validation

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10.1016/j.nucengdes.2023.112392

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title = "Comparison of calculated and measured spent nuclear fuel decay heat with CASMO5, SNF and standard methods",

abstract = "In this paper, we present a comparison between measured and calculated decay values for spent nuclear fuel assemblies from the Clab, GE-Morris EMAD facilities. Two codes are applied: CASMO5 and SNF, using different nuclear data libraries (JEF-2.2, JEFF-3.1.1, JEFF-3.2, ENDF/B-VII.1 and ENDF/B-VIII.0) and different code versions. Additionally values from four standard and guides for calculation of decay heats (ANS 2014, DIN 2014, ISO 2022 and RG-3.54 2018) were also compared with the measurements. All simulations with different codes, code versions and methods are based on the same geometry and irradiation descriptions for a single assembly, providing more convenient comparisons of results. The impact of nuclear data libraries and computational methods are shown, compared to the spread of C/E (Calculations over Experiment) values between the 256 considered measurements. Finally, a comparison of the most important nuclides contributing to the decay heat is presented between measured assemblies and more recent cases corresponding to higher burnup, initial enrichment and longer cooling times.",

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AU - Taforeau, J.

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N2 - In this paper, we present a comparison between measured and calculated decay values for spent nuclear fuel assemblies from the Clab, GE-Morris EMAD facilities. Two codes are applied: CASMO5 and SNF, using different nuclear data libraries (JEF-2.2, JEFF-3.1.1, JEFF-3.2, ENDF/B-VII.1 and ENDF/B-VIII.0) and different code versions. Additionally values from four standard and guides for calculation of decay heats (ANS 2014, DIN 2014, ISO 2022 and RG-3.54 2018) were also compared with the measurements. All simulations with different codes, code versions and methods are based on the same geometry and irradiation descriptions for a single assembly, providing more convenient comparisons of results. The impact of nuclear data libraries and computational methods are shown, compared to the spread of C/E (Calculations over Experiment) values between the 256 considered measurements. Finally, a comparison of the most important nuclides contributing to the decay heat is presented between measured assemblies and more recent cases corresponding to higher burnup, initial enrichment and longer cooling times.

AB - In this paper, we present a comparison between measured and calculated decay values for spent nuclear fuel assemblies from the Clab, GE-Morris EMAD facilities. Two codes are applied: CASMO5 and SNF, using different nuclear data libraries (JEF-2.2, JEFF-3.1.1, JEFF-3.2, ENDF/B-VII.1 and ENDF/B-VIII.0) and different code versions. Additionally values from four standard and guides for calculation of decay heats (ANS 2014, DIN 2014, ISO 2022 and RG-3.54 2018) were also compared with the measurements. All simulations with different codes, code versions and methods are based on the same geometry and irradiation descriptions for a single assembly, providing more convenient comparisons of results. The impact of nuclear data libraries and computational methods are shown, compared to the spread of C/E (Calculations over Experiment) values between the 256 considered measurements. Finally, a comparison of the most important nuclides contributing to the decay heat is presented between measured assemblies and more recent cases corresponding to higher burnup, initial enrichment and longer cooling times.

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Comparison of calculated and measured spent nuclear fuel decay heat with CASMO5, SNF and standard methods

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