The Proceedings of the National Symposium on Power and Energy Systems
Online ISSN : 2424-2950
2021.25
Session ID : A212
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Improvement of integrative severe accident analysis code, SPECTRA
(Discussion of specifications of evaluating module for core disruptive accident)
*Ken-ichi KAWADATakashi TAKATATohru SUZUKI
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Abstract

In the severe accident evaluation of sodium-cooled fast reactors (SFRs), a module to analyze core disruptive accidents (CDAs) from the initiating phase to the transition phase of various cores has been developed for the purpose of consistent evaluation of the entire accident process from the initial to the final state. In this paper, the physical phenomena in steady-state irradiation and CDA events of mixed oxide (MOX) fuel and metallic fuel of sodium-cooled fast reactors are summarized and the functions to be included in the analysis module are discussed. For both fuel compositions, the deformation of the core material due to the accumulated FP gas in the fuel caused by neutron irradiation and the post-failure migration were the main important issues. Eutectic and extrusion are also important issues as features of metallic fuels.

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© 2021 The Japan Society of Mechanical Engineers
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