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Sahboun, N. F.; Matsumoto, Toshinori; Iwasawa, Yuzuru; Sugiyama, Tomoyuki
Proceedings of Asian Symposium on Risk Assessment and Management 2021 (ASRAM 2021) (Internet), 15 Pages, 2021/10
Li, C.-Y.; Uchibori, Akihiro; Takata, Takashi; Pellegrini, M.*; Erkan, N.*; Okamoto, Koji*
Dai-25-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet), 4 Pages, 2021/07
The capability of stable cooling and avoiding re-criticality on the debris bed are the main issues for achieving IVR (In-Vessel Retention). In the actual situation, the debris bed is composed of mixed-density debris particles. Hence, when these mixed-density debris particles were launched to re-distribute, the debris bed would possibly form a density-stratified distribution. For the proper evaluation of this scenario, the multi-physics model of CFD-DEM-Monte-Carlo based neutronics is established to investigate the coolability and re-criticality on the heterogeneous density-stratified debris bed with considering the particle relocation. The CFD-DEM model has been verified by utilizing water injection experiments on the mixed-density particle bed in the first portion of this research. In the second portion, the coupled system of the CFD-DEM-Monte-Carlo based neutronics model is applied to reactor cases. Afterward, the debris particles' movement, debris particles' and coolant's temperature, and the k-eff eigenvalue are successfully tracked. Ultimately, the relocation and stratification effects on debris bed's coolability and re-criticality had been quantitatively confirmed.
Uesawa, Shinichiro; Shibata, Mitsuhiko; Yamashita, Susumu; Yoshida, Hiroyuki
Proceedings of 10th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-10) (USB Flash Drive), 7 Pages, 2016/11
Maruyama, Yu*; Moriyama, Kiyofumi; Nakamura, Hideo; Hirano, Masashi; Nakajima, K.*
Journal of Nuclear Science and Technology, 40(1), p.12 - 21, 2003/01
Times Cited Count：6 Percentile：41.75(Nuclear Science & Technology)no abstracts in English
Maruyama, Yu; Moriyama, Kiyofumi; Nakamura, Hideo; Hashimoto, Kazuichiro; Hirano, Masashi; Nakajima, K.*
Proceedings of RASPLAV Seminar 2000 (CD-ROM), 8 Pages, 2000/11
no abstracts in English
Maruyama, Yu; ; Moriyama, Kiyofumi; H.S.Park*; Kudo, Tamotsu; Y.Yang*; Sugimoto, Jun
Nucl. Eng. Des., 187(2), p.241 - 254, 1999/00
Times Cited Count：20 Percentile：79.79(Nuclear Science & Technology)no abstracts in English
21, 1997, Tokai-mura, Japan*; ; Sugimoto, Jun
JAERI-Conf 97-011, 829 Pages, 1998/01
no abstracts in English
Maruyama, Yu; ; Moriyama, Kiyofumi; H.S.Park*; Kudo, Tamotsu; Y.Yang*; Sugimoto, Jun
JAERI-Conf 98-009, p.100 - 106, 1998/00
no abstracts in English
Maruyama, Yu; Yamano, Norihiro; Kudo, Tamotsu; Moriyama, Kiyofumi; Sugimoto, Jun
JAERI-memo 08-127, p.269 - 275, 1996/06
no abstracts in English
Maruyama, Yu; Yamano, N.; Moriyama, Kiyofumi; H.S.Park*; Kudo, Tamotsu; Sugimoto, Jun
NUREG/CP-0157, 2, p.161 - 172, 1996/00
no abstracts in English
Maruyama, Yu; Yamano, N.; Moriyama, Kiyofumi; H.S.Park*; Kudo, Tamotsu; Sugimoto, Jun
Proc. of Int. Topical Meeting on Probabilistic Safety Assessment (PSA96), 3, p.1367 - 1374, 1996/00
no abstracts in English
Maruyama, Yu; Yamano, N.; Kudo, Tamotsu; Hidaka, Akihide; Sugimoto, Jun
NEA/CSNI/R(95)3, 0, p.223 - 240, 1995/07
no abstracts in English
Sugimoto, Jun
Dennetsu Kenkyu, 34(133), p.52 - 59, 1995/04
no abstracts in English
Maruyama, Yu; Yamano, N.; Kudo, Tamotsu; Moriyama, Kiyofumi; Sugimoto, Jun
Proc., Seminar on the Vapor Explosions in Nuclear Power Safety,Kanzanji 1995, 0, p.54 - 69, 1995/00
no abstracts in English
Sato, Ikken
no journal, ,
It is necessary to maximize the knowledge with: (1) In-depth data analysis of 1F plant data, (2) Well-targeted experiments addressing the BWR-specific uncertainties, and (3) Evaluation of accident progression behavior based on integration of all the available information. In-depth analysis of Unit 2 and Unit 3 plant data was conducted as step (1). This step provided outlines of accident progression behavior in these units. This information is then reflected into SA code analyses. A series of plasma heating experiments using a test section simulating a part of BWR core were conducted to get insights for the above step (2). Core material relocation behavior in the high-temperature range up to ceramic fuel melting was observed in these tests. The above step (3) consisted of an evaluation of core thermal energy for Unit 2 and Unit 3.
