Model integration of the ex-vessel modules for the SFR safety analysis code SPECTRA

Author:

AOYAGI Mitsuhiro1,MAKINO Tohru2,OHKI Hiroshi3,UCHIBORI Akihiro1,OKANO Yasushi1

Affiliation:

1. Japan Atomic Energy Agency

2. NESI corporation

3. NDD corporation

Publisher

Japan Society of Mechanical Engineers

Reference14 articles.

1. Aoyagi, M., Louie, D. L. Y. Uchibori, A., Takata, T. and Luxat, D., Study of Recent Sodium Pool Fire Model Improvements for MELCOR Code, Proceedings of the 28th International Conference on Nuclear Engineering (ICONE-28), ICONE2021-64509 (2021), DOI: 10.1115/ICONE28-64509.

2. Aoyagi, M., Uchibori, A. and Takata, T, Development of the Sodium Pool and Floor Concrete Module for the Integrated SFR Safety Analysis Code, SPECTRA, Proceedings of the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), On-line virtual, March 6-11, Log nr.: 35340 (2022).

3. Cole, R. K., CORCON-Mod2: A Computer Program for Analysis of Molten-Core Concrete Interactions, SAND84-1246, NUREG/CR-3920 (1984).

4. Futagami, S., Nishimura, M., Kawata., K., Ishikawa., H. and Miyahara, S., Sodium Pool Combustion Test Run-F7 (Interim Report), PNC Report, PNC TN9410 98-074, Power Reactor and Nuclear Fuel Development Corporation, Oarai, Japan, August (1998) (in Japanese).

5. Girault, N., Cloarec, L., Herranz, L., Bandini, G., Perez-Martin, S. and Ammirabile, L., On-going activities in the European JASMIN project for the development and validation of ASTEC-Na safety simulation code, Proceedings of 2015 International Congress on Advances in Nuclear Power Plants (ICAPP’15), Nice, France, May 3-6 (2015), pp. 482-494.

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