R & D of the next generation safety analysis methods for fast reactors with new computational science and technology (2) development and verification of thermo-hydrodynamics module of the compass code

Yuichi Yamamoto; Etsujo Hirano; Masaya Oue; Sensuke Shimizu; Noriyuki Shirakawa; Seiichi Koshizuka; Koji Morita

R & D of the next generation safety analysis methods for fast reactors with new computational science and technology (2) development and verification of thermo-hydrodynamics module of the compass code

Yuichi Yamamoto, Etsujo Hirano, Masaya Oue, Sensuke Shimizu, Noriyuki Shirakawa, Seiichi Koshizuka, Koji Morita

Nuclear Energy Systems

Research output: Chapter in Book/Report/Conference proceeding › Conference 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 sodium-cooled fast reactors (SFR5). The COMPASS is designed to analyze multi-physics problems involving thermal hydraulics, structure and phase change, in a unified framework of MPS method. In FY2006, development of the basic functions of the COMPASS was completed and fundamental verification calculations are being carried out at the moment. In this paper, we describe the conceptual design of COMPASS and the outline of the formulation of MPS method, and show the results of the basic verification calculations for thermo -hydrodynamics module.

Original language	English
Title of host publication	2008 Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16
Pages	359-367
Number of pages	9
Publication status	Published - 2008
Event	16th International Conference on Nuclear Engineering, ICONE16 2008 - Orlando, FL, United States Duration: May 11 2008 → May 15 2008

Publication series

Name	International Conference on Nuclear Engineering, Proceedings, ICONE
Volume	2

Other

Other	16th International Conference on Nuclear Engineering, ICONE16 2008
Country/Territory	United States
City	Orlando, FL
Period	5/11/08 → 5/15/08

All Science Journal Classification (ASJC) codes

Nuclear Energy and Engineering

Cite this

Yamamoto, Y., Hirano, E., Oue, M., Shimizu, S., Shirakawa, N., Koshizuka, S., & Morita, K. (2008). R & D of the next generation safety analysis methods for fast reactors with new computational science and technology (2) development and verification of thermo-hydrodynamics module of the compass code. In 2008 Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16 (pp. 359-367). (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 2).

R & D of the next generation safety analysis methods for fast reactors with new computational science and technology (2) development and verification of thermo-hydrodynamics module of the compass code. / Yamamoto, Yuichi; Hirano, Etsujo; Oue, Masaya et al.
2008 Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16. 2008. p. 359-367 (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 2).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

Yamamoto, Y, Hirano, E, Oue, M, Shimizu, S, Shirakawa, N, Koshizuka, S & Morita, K 2008, R & D of the next generation safety analysis methods for fast reactors with new computational science and technology (2) development and verification of thermo-hydrodynamics module of the compass code. in 2008 Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16. International Conference on Nuclear Engineering, Proceedings, ICONE, vol. 2, pp. 359-367, 16th International Conference on Nuclear Engineering, ICONE16 2008, Orlando, FL, United States, 5/11/08.

Yamamoto Y, Hirano E, Oue M, Shimizu S, Shirakawa N, Koshizuka S et al. R & D of the next generation safety analysis methods for fast reactors with new computational science and technology (2) development and verification of thermo-hydrodynamics module of the compass code. In 2008 Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16. 2008. p. 359-367. (International Conference on Nuclear Engineering, Proceedings, ICONE).

Yamamoto, Yuichi ; Hirano, Etsujo ; Oue, Masaya et al. / R & D of the next generation safety analysis methods for fast reactors with new computational science and technology (2) development and verification of thermo-hydrodynamics module of the compass code. 2008 Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16. 2008. pp. 359-367 (International Conference on Nuclear Engineering, Proceedings, ICONE).

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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 sodium-cooled fast reactors (SFR5). The COMPASS is designed to analyze multi-physics problems involving thermal hydraulics, structure and phase change, in a unified framework of MPS method. In FY2006, development of the basic functions of the COMPASS was completed and fundamental verification calculations are being carried out at the moment. In this paper, we describe the conceptual design of COMPASS and the outline of the formulation of MPS method, and show the results of the basic verification calculations for thermo -hydrodynamics module.",

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R & D of the next generation safety analysis methods for fast reactors with new computational science and technology (2) development and verification of thermo-hydrodynamics module of the compass code

Abstract

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Other

All Science Journal Classification (ASJC) codes

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