The Proceedings of the National Symposium on Power and Energy Systems
Online ISSN : 2424-2950
2021.25
Session ID : A211
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Development of Severe Accident Integrated Analysis code, SPECTRA for Sodium-cooled Fast Reactors
*Akihiro UCHIBORIMasateru SONEHARAMitsuhiro AOYAGIKen-ichi KAWADATakashi TAKATAHiroyuki OHSHIMA
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Abstract

Progress of severe accidents (SAs) has been previously evaluated by transferring analytical results between multiple analysis codes. In this study, a new analysis code, SPECTRA was developed for integrated analysis of in- and ex-vessel phenomena during SAs. SPECTRA consists of in- and ex-vessel modules which have a thermal hydraulics (TH) module as a base part. The in-vessel TH module computes complicated multi-dimensional behavior of liquid sodium and gas by using the multi-fluid model considering compressibility. Relocation of a molten core is computed by the dissipative particle dynamics method. A lumped mass model was employed for computation of ex-vessel multi-component gas flow including aerosols. The fully implicit scheme was applied to both the TH modules to enable computation with a large time step width. Analytical models for sodium fire, sodium-concrete interaction, and debris-concrete interaction were integrated into the ex-vessel module. The in- and ex-vessel modules were coupled by exchanging the amount of leaked sodium and debris at every time step. Basic capability of SPECTRA was demonstrated through analysis of a loss of reactor level event.

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© 2021 The Japan Society of Mechanical Engineers
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