2017 Annual Meeting

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Oral presentation

III. Fission Energy Engineering » 304-1 Thermal Hydraulics, Energy Conversion, Energy Transfer, Energy Storage

[1K09-13] Liquid-Metal Thermal Hydraulics

Mon. Mar 27, 2017 3:50 PM - 5:10 PM Room K (16-306 Building No.16)

Chair: Shinji Ebara (Tohoku Univ.)

3:50 PM - 4:05 PM

[1K09] Advancement of Sodium-water Reaction Phenomenon Analysis Code SERAPHIM

Application of Unstructured Mesh-based Numerical Method

*Akihiro Uchibori1, Akira Watanabe2, Takashi Takata1, Hiroyuki Ohshima1 (1. JAEA, 2. NDD)

Keywords:Sodium-cooled fast reactor, Steam generator, Sodium-water reaction, Numerical analysis, Unstructured mesh

A sodium-water reaction analysis code SERAPHIM has been developed to evaluate tube failure accident in a steam generator of sodium-cooled fast reactors. In this study, an unstructured mesh-based numerical method was applied to the SERAPHIM code to advance a numerical accuracy. The basic validity of the proposed method was confirmed.