Impact of ENDF/B-VIII.0 library on BR2 depletion calculations for irradiation testing of low-enriched uranium silicide dispersion fuel

Andrei Rykhlevskii; Aurelien Bergeron; Francesc Puig; Jeremy Licht; Silva Kalcheva; Geert Van den Branden

doi:10.13182/T130-44471

Impact of ENDF/B-VIII.0 library on BR2 depletion calculations for irradiation testing of low-enriched uranium silicide dispersion fuel

Andrei Rykhlevskii, Aurelien Bergeron, Francesc Puig, Jeremy Licht, Silva Kalcheva, Geert Van den Branden

Reactor Control and Experiments

Research output › peer-review

Abstract

The 2018 release of the Evaluated Nuclear Data File ENDF/B-VIII.0 library [1] motivated several examinations of the impact of the revised nuclear data on established Monte Carlo models of various reactors. ENDF/B-VIII.0 has
multiple notable updates over ENDF/B-VII.0 [2] currently used by Argonne National Laboratory (Argonne) for depletion calculations of current and upcoming test fuel
irradiations in Belgian Reactor 2 (BR2). Of relevance, differences exist in the 235U, 238U, and 239Pu capture and fission cross-sections. The scattering and capture crosssections of 1H, 16O, 9Be, 27Al, and 56Fe show differences as well, which might affect the calculations.

Original language	English
Title of host publication	Transactions of the American Nuclear Society
Pages	1048-1051
Number of pages	4
Volume	130
Edition	1
DOIs	https://doi.org/10.13182/T130-44471
State	Published - Jun 2024
Event	2024 Annual Conference on Transactions of the American Nuclear Society, ANS 2024 - Las Vegas Duration: 16 Jun 2024 → 19 Jun 2024

Publication series

Name	Transactions of the American Nuclear Society
Publisher	American Nuclear Society
ISSN (Print)	0003-018X

Conference

Conference	2024 Annual Conference on Transactions of the American Nuclear Society, ANS 2024
Country/Territory	United States
City	Las Vegas
Period	2024-06-16 → 2024-06-19

ASJC Scopus subject areas

Nuclear Energy and Engineering
Safety, Risk, Reliability and Quality

Access to Document

10.13182/T130-44471

Cite this

Rykhlevskii, A., Bergeron, A., Puig, F., Licht, J., Kalcheva, S., & Van den Branden, G. (2024). Impact of ENDF/B-VIII.0 library on BR2 depletion calculations for irradiation testing of low-enriched uranium silicide dispersion fuel. In Transactions of the American Nuclear Society (1 ed., Vol. 130, pp. 1048-1051). (Transactions of the American Nuclear Society). https://doi.org/10.13182/T130-44471

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title = "Impact of ENDF/B-VIII.0 library on BR2 depletion calculations for irradiation testing of low-enriched uranium silicide dispersion fuel",

abstract = "The 2018 release of the Evaluated Nuclear Data File ENDF/B-VIII.0 library [1] motivated several examinations of the impact of the revised nuclear data on established Monte Carlo models of various reactors. ENDF/B-VIII.0 has multiple notable updates over ENDF/B-VII.0 [2] currently used by Argonne National Laboratory (Argonne) for depletion calculations of current and upcoming test fuel irradiations in Belgian Reactor 2 (BR2). Of relevance, differences exist in the 235U, 238U, and 239Pu capture and fission cross-sections. The scattering and capture crosssections of 1H, 16O, 9Be, 27Al, and 56Fe show differences as well, which might affect the calculations.",

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author = "Andrei Rykhlevskii and Aurelien Bergeron and Francesc Puig and Jeremy Licht and Silva Kalcheva and \{Van den Branden\}, Geert",

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Rykhlevskii, A, Bergeron, A, Puig, F, Licht, J, Kalcheva, S & Van den Branden, G 2024, Impact of ENDF/B-VIII.0 library on BR2 depletion calculations for irradiation testing of low-enriched uranium silicide dispersion fuel. in Transactions of the American Nuclear Society. 1 edn, vol. 130, Transactions of the American Nuclear Society, pp. 1048-1051, 2024 Annual Conference on Transactions of the American Nuclear Society, ANS 2024, Las Vegas, United States, 2024-06-16. https://doi.org/10.13182/T130-44471

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