Validation study of sodium pool fire modeling efforts in MELCOR and SPHINCS codes-Reference-Cited by-同舟云学术

Validation study of sodium pool fire modeling efforts in MELCOR and SPHINCS codes

Published:2023-06 Issue: Volume:407 Page:112285
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Louie David L.Y.^ORCID,Aoyagi Mitsuhiro,Uchibori Akihiro,Takata Takashi,Luxat David L.

Funder

U.S. Department of Energy

National Nuclear Security Administration

Japan Atomic Energy Agency

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference6 articles.

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2. Miyahara, SSodium Pool Combustion Test Run-F7 (Interim Report), PNC TN9410 98–074;Futagami,1998

3. Humphries, L., Beeny, B., Louie, D.L.Y., Esmaili, H., Salay, M., Non-LWR Model Development for the MELCOR Code. In: Proceedings of the 26th International Conference on Nuclear Engineering (ICONE26), ICONE26-82415 (2018). https://doi.org/10.1115/ICONE26-82415.

4. Louie, D.L.Y., Aoyagi, M., 2021. Sodium Fire Collaborative Study Progress–CNWG Fiscal Year 2020, SAND2021-0136, Sandia National Laboratories, Albuquerque, NM, USA. https://doi.org/10.2172/1761299.

5. Murata, K.K., Carroll, D.E., Washington, K.E., Gelbard, F., Valdez, G.D., Williams, D.C., Bergeron, K.D., 1989. User’s Manual for CONTAIN 1.1, A Computer Code for Sever Nuclear Reactor Accident Containment Analysis, SAND87-2309 / NUREG/CR-5026. https://doi.org/10.2172/5199155.