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C powder and BC pellet regarding the eutectic reaction with stainless steelHong, Z.*; Ahmed, Z.*; Pellegrini, M.*; Yamano, Hidemasa; Erkan, N.*; Sharma, A. K.*; Okamoto, Koji*
Progress in Nuclear Energy, 171, p.105160_1 - 105160_13, 2024/06
In this study, it is found that the eutectic reaction between BC powder and stainless steel (SS) is considerably more rapid than that between the BC pellet and SS. The derived reaction rate constant values for powder and pellet cases are consistently based on the reference values. Also, a composition analysis using SEM/EDS was conducted for the detailed microstructures of the powder and pellet samples. In the powder case, only one thick layer is found as the reaction layer consisting of (Fe, Cr)B precipitate, including BC powder. In the pellet case, two layers are found in the reaction layer.
Hong, Z.*; Pellegrini, M.*; Erkan, N.*; Liao, H.*; Yang, H.*; Yamano, Hidemasa; Okamoto, Koji*
Annals of Nuclear Energy, 180, p.109462_1 - 109462_9, 2023/01
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)A series of experiments were conducted using BC material and SUS304 tubes as a simulant of the real control rods. Reaction rate constant data in the 1450K-1500K range were obtained, and are consistent with the reference values. The reaction layer microstructure observation and the associated chemical composition analysis were also carried onto the experiment samples.
Yamano, Hidemasa; Takai, Toshihide; Emura, Yuki; Fukuyama, Hiroyuki*; Higashi, Hideo*; Nishi, Tsuyoshi*; Ota, Hiromichi*; Morita, Koji*; Nakamura, Kinya*; Fukai, Hirofumi*; et al.
Proceedings of 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-13) (Internet), 12 Pages, 2022/09
This paper describes the project overview and progress of experimental and analytical studies conducted until 2020. Specific results in this paper are the measurement of the eutectic reaction rates and the validation of physical model describing the eutectic reaction in the analysis code through the numerical analysis of the BC-SS eutectic reaction rate experiments in which a BC pellet was placed in a SS crucible.
Bachrata, A.*; Gentet, D.*; Bertrand, F.*; Marie, N.*; Kubota, Ryuzaburo*; Sogabe, Joji; Sasaki, Keisuke; Kamiyama, Kenji; Yamano, Hidemasa; Kubo, Shigenobu
Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Sustainable Clean Energy for the Future (FR22) (Internet), 9 Pages, 2022/04
In the frame of France-Japan collaboration, one of the objectives is to define and assess the calculation methodologies, and to investigate the phenomenology and the consequences of severe accident scenarios in sodium fast reactors (SFRs). A methodology whose purpose is to assess the loadings of the structures induced by a Fuel Coolant Interaction (FCI) taking place in the sodium plenum of SFR has been defined in the frame of the collaboration between France and Japan during 2014-2019. The work progress will be spread over the period 2020-2024 and the main objectives and milestones will be introduced in the paper. The objective of studies is to comprehensively address the margin between the limit of integrity of the main vessel structures and the loadings resulting from severe accidents. For this purpose, the SIMMER mechanistic calculation code simulates core disruptive accident sequences in SFRs. A fluid structure dynamics tool evaluates this interaction i.e. EUROPLEXUS is used in CEA studies and AUTODYN tool is used in JAEA studies. In the paper, a benchmark study is described in order to illustrate the evaluation of vapour expansion phase in the hot plenum. To do that, joint input data are used on the basis of an ASTRID 1500 MWth core degraded state after the power excursion which leads to vapour expansion. The most penalizing case was evidenced in this study by suppressing the action of transfer tube in-core mitigation devices in SIMMER input deck and thus privileging the upward molten core ejection. Even if the most penalizing case was evidenced in this paper, no significant RV deformation was observed in both EUROPLEXUS and AUTODYN calculation results. The assumed mechanical energy was small for the core expansion phase.
Matsuo, Eiji*; Sasa, Kyohei*; Koyama, Kazuya*; Yamano, Hidemasa; Kubo, Shigenobu; Hourcade, E.*; Bertrand, F.*; Marie, N.*; Bachrata, A.*; Dirat, J. F.*
Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 5 Pages, 2019/05
Discharged molten-fuel from the core during Core Disruptive Accident (CDA) could become solidified particle debris by fuel-coolant interaction in the lower sodium plenum, and then the debris could form a bed on a core catcher located at the bottom of the reactor vessel. Coolability evaluations for the debris bed are necessary for the design of the core catcher. The purpose of this study is to evaluate the coolability of the debris bed on the core catcher for the ASTRID design. For this purpose, as a first step, the coolability calculations of the debris beds formed both in short term and later phase have been performed by modeling only the debris bed itself. Thus, details of core catcher design and decay heat removal system are not described in this paper. In all the calculations, coolant temperature around the debris bed is a parameter. The calculation tool is the debris bed module implemented into a one-dimensional plant dynamics code, Super-COPD. The evaluations have shown that the debris beds formed both in short term and later phase are coolable by the design which secures sufficient coolant flow around the core catcher located in the cold pool.
H.-S.Park*; Yamano, N.; Maruyama, Yu; Moriyama, Kiyofumi; Kudo, Tamotsu; Sugimoto, Jun
JAERI-Review 96-018, 46 Pages, 1996/11
JAERI-Review-96-018.pdf:1.99MB
no abstracts in English
; Abe, Yutaka*; *; *; Yamano, N.; Sugimoto, Jun
JAERI-Research 96-032, 152 Pages, 1996/06
JAERI-Research-96-032.pdf:4.05MB
no abstracts in English
Yamano, N.; Maruyama, Yu; Moriyama, Kiyofumi; Sugimoto, Jun
NEA/CSNI/R(96)24, 0, p.1 - 49, 1996/00
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
Yamano, N.; Maruyama, Yu; Moriyama, Kiyofumi; Kudo, Tamotsu; H.S.Park*; Sugimoto, Jun
Proc. of 11th KAIF/KNS Annual Conf., 0, p.827 - 838, 1996/00
no abstracts in English
Moriyama, Kiyofumi; Yamano, N.; Maruyama, Yu; Kudo, Tamotsu; Sugimoto, Jun
Proc. of ASME
JSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 1(PART B), p.903 - 915, 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
Sugimoto, Jun; Uetsuka, Hiroshi; Hidaka, Akihide; Maruyama, Yu; Yamano, N.; Hashimoto, Kazuichiro
Thermophysical Properties 17 (17th Japan Symp. 1996), 0, p.163 - 166, 1996/00
no abstracts in English
Moriyama, Kiyofumi; Yamano, N.; Maruyama, Yu; Kudo, Tamotsu; *; *; Sugimoto, Jun
JAERI-Data/Code 95-016, 50 Pages, 1995/11
JAERI-Data-Code-95-016.pdf:1.61MB
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
Moriyama, Kiyofumi; Yamano, N.; Maruyama, Yu; Kudo, Tamotsu; *; *; Sugimoto, Jun
Proc., Seminar on the Vapor Explosions in Nuclear Power Safety,Kanzanji 1995, p.87 - 102, 1995/00
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
Yamano, N.; Moriyama, Kiyofumi; Maruyama, Yu; Kudo, Tamotsu; Sugimoto, Jun
Proc., Seminar on the Vapor Explosions in Nuclear Power Safety,Kanzanji 1995, 0, p.121 - 139, 1995/00
no abstracts in English
*; *; Maruyama, Yu; Yamano, N.; Sugimoto, Jun
Transactions of 13th International Conference on Structural Mechanics in Reactor Technology (SMiRT-13), 4, p.359 - 370, 1995/00
no abstracts in English
Moriyama, Kiyofumi; Yamano, N.; Maruyama, Yu; Kudo, Tamotsu; Sugimoto, Jun
JAERI-Review 94-010, 40 Pages, 1994/12
JAERI-Review-94-010.pdf:1.51MB
no abstracts in English
