Advanced modeling of multicomponent vaporization/condensation phenomena for a reactor safety analysis code SIMMER-III

Koji Morita, Tatsuya Matsumoto, Ryo Akasaka, Kenji Fukuda, Tohru Suzuki, Yoshiharu Tobita, Hidemasa Yamano, Satoru Kondo

Research output: Contribution to conferencePaper

Abstract

It is believed that the numerical simulation of thermal-hydraulic phenomena of multiphase, multicomponent flows in a reactor core is essential to investigate core disruptive accidents (CDAs) of liquid-metal fast reactors. A new multicomponent vaporization/condensation (V/C) model was developed to provide a generalized model for a fast reactor safety analysis code SIMMER-III, which analyzes relatively short-time-scale phenomena relevant to accident sequences of CDAs. The model characterizes the V/C process associated with phase transition through heat-transfer and mass-diffusion limited models to follow the time evolution of the reactor core under CDA conditions. The heat-transfer limited model describes the nonequilibrium phase-transition processes occurring at interfaces, while the mass-diffusion limited model is employed to represent effects of noncondensable gases and multicomponent mixture on V/C processes. Verification of the model and method employed in the multicomponent V/C model of SIMMER-III was performed successfully by analyzing two series of condensation experiments.

Original languageEnglish
Pages351-358
Number of pages8
DOIs
Publication statusPublished - Oct 19 2002
Event10th International Conference on Nuclear Engineering (ICONE 10) - Arlington, VA, United States
Duration: Apr 14 2002Apr 18 2002

Other

Other10th International Conference on Nuclear Engineering (ICONE 10)
CountryUnited States
CityArlington, VA
Period4/14/024/18/02

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All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

Cite this

Morita, K., Matsumoto, T., Akasaka, R., Fukuda, K., Suzuki, T., Tobita, Y., ... Kondo, S. (2002). Advanced modeling of multicomponent vaporization/condensation phenomena for a reactor safety analysis code SIMMER-III. 351-358. Paper presented at 10th International Conference on Nuclear Engineering (ICONE 10), Arlington, VA, United States. https://doi.org/10.1115/ICONE10-22229