A hybrid approach for neutronics calculations in the neutron shielding of sodium fast reactors

Neutron calculations in the neutron shielding of fast neutron reactors are a complex problem as deterministic schemes are usually not suited for such calculations while Monte-Carlo codes have poor computational performance due to the very low flux levels in neutron shields. In this article, both met...

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Autores principales:	Hajji Amine, Coquelet-Pascal Christine, Blaise Patrick
Formato:	article
Lenguaje:	EN
Publicado:	EDP Sciences 2021
Materias:	Nuclear engineering. Atomic power TK9001-9401
Acceso en línea:	https://doaj.org/article/81211d9c6695440f8eb456bb0efb83b4
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id	oai:doaj.org-article:81211d9c6695440f8eb456bb0efb83b4
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spelling	oai:doaj.org-article:81211d9c6695440f8eb456bb0efb83b42021-11-08T15:20:00ZA hybrid approach for neutronics calculations in the neutron shielding of sodium fast reactors2491-929210.1051/epjn/2021016https://doaj.org/article/81211d9c6695440f8eb456bb0efb83b42021-01-01T00:00:00Zhttps://www.epj-n.org/articles/epjn/full_html/2021/01/epjn200025/epjn200025.htmlhttps://doaj.org/toc/2491-9292Neutron calculations in the neutron shielding of fast neutron reactors are a complex problem as deterministic schemes are usually not suited for such calculations while Monte-Carlo codes have poor computational performance due to the very low flux levels in neutron shields. In this article, both methods are studied, as well as a hybrid scheme on the neutron shielding of the ASTRID fast reactor benchmark. This hybrid scheme uses a fission source calculated by a deterministic code in order to precisely calculate neutron fluxes in the shielding with a Monte-Carlo code using variance reduction techniques. This provides reference results in order to validate deterministic calculations. Comparisons between deterministic codes and this hybrid reference show that large biases are obtained, up to 50%. Further studies are made to reduce the biases, showing that many physical phenomena should be treated, including anisotropy of the scattering law at high energies and spatial self-shielding inside the boron carbide shielding. These improvements reduce the biases to less than 10%. Finally, some applications to designing criteria for the neutron shielding are presented, such as gas production in the neutron shielding and activation of secondary sodium at the intermediate heat exchanger (IHX).Hajji AmineCoquelet-Pascal ChristineBlaise PatrickEDP SciencesarticleNuclear engineering. Atomic powerTK9001-9401ENEPJ Nuclear Sciences & Technologies, Vol 7, p 17 (2021)
institution	DOAJ
collection	DOAJ
language	EN
topic	Nuclear engineering. Atomic power TK9001-9401
spellingShingle	Nuclear engineering. Atomic power TK9001-9401 Hajji Amine Coquelet-Pascal Christine Blaise Patrick A hybrid approach for neutronics calculations in the neutron shielding of sodium fast reactors
description	Neutron calculations in the neutron shielding of fast neutron reactors are a complex problem as deterministic schemes are usually not suited for such calculations while Monte-Carlo codes have poor computational performance due to the very low flux levels in neutron shields. In this article, both methods are studied, as well as a hybrid scheme on the neutron shielding of the ASTRID fast reactor benchmark. This hybrid scheme uses a fission source calculated by a deterministic code in order to precisely calculate neutron fluxes in the shielding with a Monte-Carlo code using variance reduction techniques. This provides reference results in order to validate deterministic calculations. Comparisons between deterministic codes and this hybrid reference show that large biases are obtained, up to 50%. Further studies are made to reduce the biases, showing that many physical phenomena should be treated, including anisotropy of the scattering law at high energies and spatial self-shielding inside the boron carbide shielding. These improvements reduce the biases to less than 10%. Finally, some applications to designing criteria for the neutron shielding are presented, such as gas production in the neutron shielding and activation of secondary sodium at the intermediate heat exchanger (IHX).
format	article
author	Hajji Amine Coquelet-Pascal Christine Blaise Patrick
author_facet	Hajji Amine Coquelet-Pascal Christine Blaise Patrick
author_sort	Hajji Amine
title	A hybrid approach for neutronics calculations in the neutron shielding of sodium fast reactors
title_short	A hybrid approach for neutronics calculations in the neutron shielding of sodium fast reactors
title_full	A hybrid approach for neutronics calculations in the neutron shielding of sodium fast reactors
title_fullStr	A hybrid approach for neutronics calculations in the neutron shielding of sodium fast reactors
title_full_unstemmed	A hybrid approach for neutronics calculations in the neutron shielding of sodium fast reactors
title_sort	hybrid approach for neutronics calculations in the neutron shielding of sodium fast reactors
publisher	EDP Sciences
publishDate	2021
url	https://doaj.org/article/81211d9c6695440f8eb456bb0efb83b4
work_keys_str_mv	AT hajjiamine ahybridapproachforneutronicscalculationsintheneutronshieldingofsodiumfastreactors AT coqueletpascalchristine ahybridapproachforneutronicscalculationsintheneutronshieldingofsodiumfastreactors AT blaisepatrick ahybridapproachforneutronicscalculationsintheneutronshieldingofsodiumfastreactors AT hajjiamine hybridapproachforneutronicscalculationsintheneutronshieldingofsodiumfastreactors AT coqueletpascalchristine hybridapproachforneutronicscalculationsintheneutronshieldingofsodiumfastreactors AT blaisepatrick hybridapproachforneutronicscalculationsintheneutronshieldingofsodiumfastreactors
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A hybrid approach for neutronics calculations in the neutron shielding of sodium fast reactors

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