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Hayashi, Masaaki*; Nakahara, Hirotaka*; Shirakura, Shota*; Yamano, Hidemasa
Proceedings of International Conference on Nuclear Fuel Cycle (GLOBAL2024) (Internet), 4 Pages, 2024/10
As part of the development of risk assessment technologies for sodium-cooled fast reactor coupled to thermal energy storage (TES) system with sodium-molten salt heat exchanger (HX), simple evaluation of heat transfer performance using heat transfer coefficient formula is performed. And Computational Fluid Dynamics (CFD) thermal analyses by STAR-CCM+ with partial HX model are performed to develop evaluation technology. The performance evaluation technology of a HX between sodium and molten salt and the confirmation of heat transfer improvement measures effects is developed.
Hayashi, Masaaki*; Nakahara, Hirotaka*; Abe, Takashi*; Matsunaga, Suhei*; Miyata, Hajime*; Shirakura, Shota*; Yamano, Hidemasa
Dai-28-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet), 5 Pages, 2024/06
This paper describes the study of the performance evaluation technology of a heat exchanger between sodium and molten salt and the confirmation of heat transfer improvement measures effects up to FY2023.
Abe, Takashi*; Nakahara, Hirotaka*; Aoyagi, Mitsuhiro
no journal, ,
no abstracts in English
Abe, Takashi*; Nakahara, Hirotaka*; Aoyagi, Mitsuhiro; Fujimata, Kazuhiro*
no journal, ,
no abstracts in English
Takata, Takashi*; Nakahara, Hirotaka*; Suzuki, Toru*; Oishi, Yuji*
no journal, ,
A safety evaluation technology which is based on the SPECTRA code for integrated analysis of in- and ex-vessel phenomena during severe accidents in sodium-cooled fast reactors has been developed. The development in the next four years includes an in-vessel lumped mass model, a core damage model, application of SPECTRA for a PRISM-type reactor, a design optimization method by artificial intelligence, a graphical user interface for input data construction, and an automation tool of quality assurance. Furthermore, thermal properties of molten fuels will be measured by a state-of-the-art technology for enlargement of basic database.
Fuchita, Sho*; Fujimata, Kazuhiro*; Abe, Takashi*; Nakahara, Hirotaka*; Aoyagi, Mitsuhiro; Ishida, Shinya
no journal, ,
no abstracts in English
Hayashi, Masaaki*; Nakahara, Hirotaka*; Abe, Takashi*; Endo, Keita*; Miyata, Hajime*; Yamano, Hidemasa
no journal, ,
As part of the development of safety design technologies for sodium-cooled fast reactor coupled to thermal energy storage system with nitrate molten salt heat exchanger, we are considering optimization of heat exchanger type and measures to improve heat transfer. We have confirmed the effect of the heat transfer performance improvement, for which we conducted Computational Fluid Dynamics analyses with the analytical model of the selected heat exchanger type.
Hayashi, Masaaki*; Nakahara, Hirotaka*; Abe, Takashi*; Yamano, Hidemasa
no journal, ,
As part of the development of safety design technologies for sodium-cooled fast reactor coupled to thermal energy storage system with sodium-molten salt heat exchanger, this study selects heat exchanger types suitable for heat exchange between sodium and molten salt with consideration of heat transfer performance improvement. This paper reports survey results on heat transfer and flow characteristics and future plan for heat transfer performance improvement of heat exchanger.
Hayashi, Masaaki*; Nakahara, Hirotaka*; Abe, Takashi*; Matsunaga, Suhei*; Shirakura, Shota*; Yamano, Hidemasa
no journal, ,
As part of the development of safety design technologies for sodium-cooled fast reactor coupled to thermal energy storage system with nitrate molten salt heat exchanger, we are considering optimization of heat exchanger type and measures to improve heat transfer. We have conducted Computational Fluid Dynamics analyses with the partial model of the selected heat exchanger type. In this presentation we present the heat transfer performance based on the analyses results.
Uchibori, Akihiro; Takata, Takashi; Nakahara, Hirotaka*; Suzuki, Toru*; Oishi, Yuji*
no journal, ,
no abstracts in English
Uchibori, Akihiro; Kawada, Kenichi; Aoyagi, Mitsuhiro; Takata, Takashi*; Nakahara, Hirotaka*; Abe, Takashi*
no journal, ,
A safety evaluation technology which is based on the SPECTRA code for integrated analysis of in- and ex-vessel phenomena during severe accidents in sodium-cooled fast reactors has been developed. The development in the next four years includes a lumped mass model of in-vessel coolant behavior, an analytical model for a passive decay heat removal system, RVACS, and application of SPECTRA for the PRISM-type reactor which is a small modular fast reactor.