Next generation safety analysis methods for SFRS (3) thermal hydraulics models of Compass code and experimental analyses

Yuichi Yamamoto, Etsujo Hirano, Masaya Oue, Sensuke Shimizu, Noriyuki Shirakawa, Seiichi Koshizuka, Koji Morita, Hidemasa Yamano, Yoshiharu Tobita

Research output: Chapter in Book/Report/Conference proceedingConference contribution

3 Citations (Scopus)

Abstract

A computer code, named COMPASS, is being developed employing the Moving Particle Semi-implicit (MPS) method for various complex phenomena of core disruptive accidents (CDAs) in the sodium-cooled fast reactors (SFRs). The COMPASS is designed to analyze multi-physics problems involving thermal hydraulics, structure and phase change, in a unified framework of MPS method. In FYs2006 and 2007 (Japanese Fiscal Year, hereafter), the development of basic functions of COMPASS was completed and fundamental verification calculations were carried out. In FY2007, the integrated verification program using available experimental data for key phenomena in CDAs was also started. In this paper, we show the basic verification calculations for the phase change model of COMPASS and the results of experimental analyses, together with the outline of the formulation of MPS method and the conceptual design of the COMPASS code.

Original languageEnglish
Title of host publicationProceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17
Pages409-418
Number of pages10
Volume5
DOIs
Publication statusPublished - 2009
Event17th International Conference on Nuclear Engineering, ICONE17 - Brussels, Belgium
Duration: Jul 12 2009Jul 16 2009

Other

Other17th International Conference on Nuclear Engineering, ICONE17
CountryBelgium
CityBrussels
Period7/12/097/16/09

Fingerprint

Hydraulic models
Core disruptive accidents
Heat problems
Hydraulic structures
Fast reactors
Conceptual design
Physics
Sodium
Hot Temperature

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

Cite this

Yamamoto, Y., Hirano, E., Oue, M., Shimizu, S., Shirakawa, N., Koshizuka, S., ... Tobita, Y. (2009). Next generation safety analysis methods for SFRS (3) thermal hydraulics models of Compass code and experimental analyses. In Proceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17 (Vol. 5, pp. 409-418) https://doi.org/10.1115/ICONE17-75521

Next generation safety analysis methods for SFRS (3) thermal hydraulics models of Compass code and experimental analyses. / Yamamoto, Yuichi; Hirano, Etsujo; Oue, Masaya; Shimizu, Sensuke; Shirakawa, Noriyuki; Koshizuka, Seiichi; Morita, Koji; Yamano, Hidemasa; Tobita, Yoshiharu.

Proceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17. Vol. 5 2009. p. 409-418.

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Yamamoto, Y, Hirano, E, Oue, M, Shimizu, S, Shirakawa, N, Koshizuka, S, Morita, K, Yamano, H & Tobita, Y 2009, Next generation safety analysis methods for SFRS (3) thermal hydraulics models of Compass code and experimental analyses. in Proceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17. vol. 5, pp. 409-418, 17th International Conference on Nuclear Engineering, ICONE17, Brussels, Belgium, 7/12/09. https://doi.org/10.1115/ICONE17-75521
Yamamoto Y, Hirano E, Oue M, Shimizu S, Shirakawa N, Koshizuka S et al. Next generation safety analysis methods for SFRS (3) thermal hydraulics models of Compass code and experimental analyses. In Proceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17. Vol. 5. 2009. p. 409-418 https://doi.org/10.1115/ICONE17-75521
Yamamoto, Yuichi ; Hirano, Etsujo ; Oue, Masaya ; Shimizu, Sensuke ; Shirakawa, Noriyuki ; Koshizuka, Seiichi ; Morita, Koji ; Yamano, Hidemasa ; Tobita, Yoshiharu. / Next generation safety analysis methods for SFRS (3) thermal hydraulics models of Compass code and experimental analyses. Proceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17. Vol. 5 2009. pp. 409-418
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