Comparative study on neutronics characteristics of a 1500 MWe metal fuel sodium-cooled fast reactor

Under the cooperative effort of the Civil Nuclear Energy R&D Working Group within the framework of the U.S.-Japan bilateral, Argonne National Laboratory (ANL) and Japan Atomic Energy Agency (JAEA) have been performing benchmark study using the Japan Sodium-cooled Fast Reactor (JSFR) design w...

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Autores principales:	Kazuya OHGAMA, Gerardo ALIBERTI, Nicolas E. STAUFF, Shigeo OHKI, Taek K. KIM
Formato:	article
Lenguaje:	EN
Publicado:	The Japan Society of Mechanical Engineers 2017
Materias:	sodium-cooled fast reactor metal fuel benchmark verification monte carlo jsfr Mechanical engineering and machinery TJ1-1570
Acceso en línea:	https://doaj.org/article/23edecbb071741e199d75423595a44e9
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spelling	oai:doaj.org-article:23edecbb071741e199d75423595a44e92021-11-26T07:03:57ZComparative study on neutronics characteristics of a 1500 MWe metal fuel sodium-cooled fast reactor2187-974510.1299/mej.16-00592https://doaj.org/article/23edecbb071741e199d75423595a44e92017-02-01T00:00:00Zhttps://www.jstage.jst.go.jp/article/mej/4/3/4_16-00592/_pdf/-char/enhttps://doaj.org/toc/2187-9745Under the cooperative effort of the Civil Nuclear Energy R&D Working Group within the framework of the U.S.-Japan bilateral, Argonne National Laboratory (ANL) and Japan Atomic Energy Agency (JAEA) have been performing benchmark study using the Japan Sodium-cooled Fast Reactor (JSFR) design with metal fuel. In this benchmark study, core characteristic parameters at the beginning of cycle were evaluated by the best estimate deterministic and stochastic methodologies of ANL and JAEA. The results obtained by both institutions show a good agreement with less than 200 pcm of discrepancy in the neutron multiplication factor, and less than 3% of discrepancy in the sodium void reactivity, Doppler reactivity, and control rod worth. The results by the stochastic and deterministic approaches were compared in each party to investigate impacts of the deterministic approximation and to understand potential variations in the results due to different calculation methodologies employed. From the detailed analysis of methodologies, it was found that the good agreement in the multiplication factor from the deterministic calculations comes from the cancellation of the differences in the methodology (0.4%) and nuclear data (0.6%). The different treatment in reflector cross section generation was estimated as the major cause of the discrepancy between the multiplication factors by the JAEA and ANL deterministic methodologies. Impacts of the nuclear data libraries were also investigated using a sensitivity analysis methodology. The differences in the inelastic scattering cross sections of U-238, ν values and fission cross sections of Pu-239 and μ-average of Na-23 are the major contributors to the difference in the multiplication factors.Kazuya OHGAMAGerardo ALIBERTINicolas E. STAUFFShigeo OHKITaek K. KIMThe Japan Society of Mechanical Engineersarticlesodium-cooled fast reactormetal fuelbenchmarkverificationmonte carlojsfrMechanical engineering and machineryTJ1-1570ENMechanical Engineering Journal, Vol 4, Iss 3, Pp 16-00592-16-00592 (2017)
institution	DOAJ
collection	DOAJ
language	EN
topic	sodium-cooled fast reactor metal fuel benchmark verification monte carlo jsfr Mechanical engineering and machinery TJ1-1570
spellingShingle	sodium-cooled fast reactor metal fuel benchmark verification monte carlo jsfr Mechanical engineering and machinery TJ1-1570 Kazuya OHGAMA Gerardo ALIBERTI Nicolas E. STAUFF Shigeo OHKI Taek K. KIM Comparative study on neutronics characteristics of a 1500 MWe metal fuel sodium-cooled fast reactor
description	Under the cooperative effort of the Civil Nuclear Energy R&D Working Group within the framework of the U.S.-Japan bilateral, Argonne National Laboratory (ANL) and Japan Atomic Energy Agency (JAEA) have been performing benchmark study using the Japan Sodium-cooled Fast Reactor (JSFR) design with metal fuel. In this benchmark study, core characteristic parameters at the beginning of cycle were evaluated by the best estimate deterministic and stochastic methodologies of ANL and JAEA. The results obtained by both institutions show a good agreement with less than 200 pcm of discrepancy in the neutron multiplication factor, and less than 3% of discrepancy in the sodium void reactivity, Doppler reactivity, and control rod worth. The results by the stochastic and deterministic approaches were compared in each party to investigate impacts of the deterministic approximation and to understand potential variations in the results due to different calculation methodologies employed. From the detailed analysis of methodologies, it was found that the good agreement in the multiplication factor from the deterministic calculations comes from the cancellation of the differences in the methodology (0.4%) and nuclear data (0.6%). The different treatment in reflector cross section generation was estimated as the major cause of the discrepancy between the multiplication factors by the JAEA and ANL deterministic methodologies. Impacts of the nuclear data libraries were also investigated using a sensitivity analysis methodology. The differences in the inelastic scattering cross sections of U-238, ν values and fission cross sections of Pu-239 and μ-average of Na-23 are the major contributors to the difference in the multiplication factors.
format	article
author	Kazuya OHGAMA Gerardo ALIBERTI Nicolas E. STAUFF Shigeo OHKI Taek K. KIM
author_facet	Kazuya OHGAMA Gerardo ALIBERTI Nicolas E. STAUFF Shigeo OHKI Taek K. KIM
author_sort	Kazuya OHGAMA
title	Comparative study on neutronics characteristics of a 1500 MWe metal fuel sodium-cooled fast reactor
title_short	Comparative study on neutronics characteristics of a 1500 MWe metal fuel sodium-cooled fast reactor
title_full	Comparative study on neutronics characteristics of a 1500 MWe metal fuel sodium-cooled fast reactor
title_fullStr	Comparative study on neutronics characteristics of a 1500 MWe metal fuel sodium-cooled fast reactor
title_full_unstemmed	Comparative study on neutronics characteristics of a 1500 MWe metal fuel sodium-cooled fast reactor
title_sort	comparative study on neutronics characteristics of a 1500 mwe metal fuel sodium-cooled fast reactor
publisher	The Japan Society of Mechanical Engineers
publishDate	2017
url	https://doaj.org/article/23edecbb071741e199d75423595a44e9
work_keys_str_mv	AT kazuyaohgama comparativestudyonneutronicscharacteristicsofa1500mwemetalfuelsodiumcooledfastreactor AT gerardoaliberti comparativestudyonneutronicscharacteristicsofa1500mwemetalfuelsodiumcooledfastreactor AT nicolasestauff comparativestudyonneutronicscharacteristicsofa1500mwemetalfuelsodiumcooledfastreactor AT shigeoohki comparativestudyonneutronicscharacteristicsofa1500mwemetalfuelsodiumcooledfastreactor AT taekkkim comparativestudyonneutronicscharacteristicsofa1500mwemetalfuelsodiumcooledfastreactor
_version_	1718409706135879680

Comparative study on neutronics characteristics of a 1500 MWe metal fuel sodium-cooled fast reactor

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