Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE
Online ISSN : 2424-2934
セッションID: ICONE19-43559
会議情報
ICONE19-43559 Development of Integrated Core Disruptive Accident Analysis Code for FBR : ASTERIA-FBR
Tomoko ISHIZUHiroshi ENDOIsao TATEWAKIToshihisa YAMAMOTONoriyuki SHIRAKAWA
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会議録・要旨集 フリー

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抄録
JNES is developing the ASTERIA-FBR code to evaluate the mechanical energy released during core disruptive accident (CDA). The code will be used for the cross-check analysis in the safety licensing procedure of the planed high performance core of MONJU. ASTERIA-FBR is a three-dimensional CDA analysis code, and consists of the three major calculation modules, CONCORD, Dynamic-GMVP, and FEMAXI. CONCORD is a fluid-dynamics calculation module with multi-phase, multi-function, and multi-velocity field model. Dynamic-GMVP is a space-time transport neutronics calculation module with multi-group Monte Calro method. FEMAXI performs thermal, mechanical, and mass transfer calculation of fuel pin during the irradiation and transient. Because of adopting the 3-D model in ASTERIA-FBR, the core can be represented by the consistent calculation meshes between the neutronics and the fluid-dynamics. This paper describes the needs of ASTERIA-FBR development, the summary of the model structures, and the model validation of CONCORD. The model validation was conducted with the experimental results of KROTOS-37 and THINA/TH562 which had been performed for the purpose to interpret fuel-coolant interaction (FCI).
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© 2011 一般社団法人 日本機械学会
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