SFR mechanical scenarios and neutron transport transients with CAST3M code

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• 作者：Grzegorz Kępisty^a ; ^{gkepisty@agh.edu.pl} ; Cyril Patricot^b ; ^{cyril.patricot@cea.fr} ; Daniel Broc^c ; ^{daniel.broc@cea.fr} ; Guillaume Campioni^b ; ^{guillaume.campioni@cea.fr}
• 关键词：SFR ; Sodium Fast Reactor ; CFSI ; Cast3M Fluid-Structure Interaction (tool) ; CNTT ; Cast3M Neutron Transport Tool ; CEA ; Atomic Energy and Alternative Energies Commission ; FSI ; Fluid-Structure Interaction ; FEM ; Finite Element Method ; LNP ; Lateral Neutron Protection ; FA ; Fuel Assembly ; CR ; Control Rod ; EOL ; End-of-Life
• 刊名：Annals of Nuclear Energy
• 出版年：2017
• 出版时间：March 2017
• 年：2017
• 卷：101
• 期：Complete
• 页码：226-236
• 全文大小：4864 K
• 卷排序：101

文摘

Several mechanical excitations of SFR core are studied using Cast3M code. The Fluid-Structure Interaction is comprised in the mechanical core model. Computed deformations are applied in Cast3M Neutron Transport Tool. Power evolution is predicted and validity of the methodology is discussed. Applied approach provides a tool for safety assessments dedicated to SFR.