In recent years, organizations both at home and abroad are actively carrying out a research on the Molten Salt Reactor systems (MSRs). For example, the Shanghai Institute of Applied Physics (SINAP), Chinese Academy of Science (CAS), is currently involved in the design and development of a 10MWth Solid Fuel Thorium Molten Salt Reactor (TMSR-SF1). SINAP started their analysis of TMSR using an earlier version of RELAP/SCDAPSIM, MOD4.0. MOD4.0 included models and correlations for molten salts but was unable to treat molten salts in the presence of non-condensable gases. Since that time SINAP and ISS have worked in parallel to extend the models and correlations for such systems. The SINAP modified code, using SINAP proprietary models and correlations, is described in the “open literature” under the name RELAP5-MSR. More general, but comparable, models developed by ISS for liquid metals/salts in the presence of non-condensable have been incorporated into RELAP/SCDAPSIM/MOD4.1. This extended option is currently being implemented for Li-Pb, Pb-Bi, molten salts, and Na.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5146-3
PROCEEDINGS PAPER
Application of RELAP/SCDAPSIM/MOD4.1 to the Analysis of Advanced Reactor/Fluid Systems With Liquid Molten Salt in the Presence of Non-Condensable Gases
M. Perez-Ferragut,
M. Perez-Ferragut
Innovative Systems Software, Ammon, ID
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J. K. Hohorst
J. K. Hohorst
Innovative Systems Software, Ammon, ID
Search for other works by this author on:
S. Jiang
Innovative Systems Software, Ammon, ID
M. Perez-Ferragut
Innovative Systems Software, Ammon, ID
Z. Fu
Innovative Systems Software, Ammon, ID
J. K. Hohorst
Innovative Systems Software, Ammon, ID
Paper No:
ICONE26-82041, V004T15A015; 9 pages
Published Online:
October 24, 2018
Citation
Jiang, S, Perez-Ferragut, M, Fu, Z, & Hohorst, JK. "Application of RELAP/SCDAPSIM/MOD4.1 to the Analysis of Advanced Reactor/Fluid Systems With Liquid Molten Salt in the Presence of Non-Condensable Gases." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation. London, England. July 22–26, 2018. V004T15A015. ASME. https://doi.org/10.1115/ICONE26-82041
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