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Pshenichnikov, A.; Kurata, Masaki; Nagae, Yuji
Proceedings of International Topical Workshop on Fukushima Decommissioning Research (FDR2022) (Internet), 4 Pages, 2022/10
The CLADS-MADE-04 is the next test in the series aiming at understanding of the melt propagation behaviour in the lower core region. In this contribution, recent results of the post-test analysis including microstructure of metallic debris investigated by Electron Probe Micro Analyzer (EPMA) are discussed. During the test, melting of the control blade happened with sudden wave of strong heat release relatively slowly (several cm/min) spread from the hottest area downwards along the degrading control blade and channel box consuming the walls made of Zircaloy-4. A significant damage happened with the sample supporting plate as well. The investigation of microstructure of such metallic debris would allow understanding of a mechanism of enhanced local core degradation. The nature of strong heat release and possibility of spreading to the surrounding materials is to be confirmed after thorough phase identification by EPMA. The difference between Fe-B eutectic debris and Zr-Fe eutectic debris will be outlined. It is especially important for understanding of the lower core plate melt-through and a possibility of a Zr-Fe molten material progression into the lower plenum.
Pshenichnikov, A.; Shibata, Hiroki; Yamashita, Takuya; Nagae, Yuji; Kurata, Masaki
Journal of Nuclear Science and Technology, 59(3), p.267 - 291, 2022/03
Times Cited Count:1 Percentile:32.89(Nuclear Science & Technology)Pshenichnikov, A.; Nagae, Yuji; Kurata, Masaki
Proceedings of TopFuel 2021 (Internet), 12 Pages, 2021/10
Pshenichnikov, A.; Kurata, Masaki; Nagae, Yuji
Journal of Nuclear Science and Technology, 58(9), p.1025 - 1037, 2021/09
Times Cited Count:2 Percentile:47.54(Nuclear Science & Technology)Pshenichnikov, A.; Nagae, Yuji; Kurata, Masaki
Proceedings of 28th International Conference on Nuclear Engineering (ICONE 28) (Internet), 7 Pages, 2021/08
Pshenichnikov, A.; Nagae, Yuji; Kurata, Masaki
Journal of Nuclear Science and Technology, 58(4), p.416 - 425, 2021/04
Times Cited Count:9 Percentile:82.73(Nuclear Science & Technology)Pshenichnikov, A.; Nagae, Yuji; Kurata, Masaki
Mechanical Engineering Journal (Internet), 7(3), p.19-00503_1 - 19-00503_10, 2020/06
Pshenichnikov, A.; Kurata, Masaki; Bottomley, D.; Sato, Ikken; Nagae, Yuji; Yamazaki, Saishun
Journal of Nuclear Science and Technology, 57(4), p.370 - 379, 2020/04
Times Cited Count:10 Percentile:66.42(Nuclear Science & Technology)Pshenichnikov, A.; Nagae, Yuji; Kurata, Masaki
Mechanical Engineering Journal (Internet), 7(2), p.19-00477_1 - 19-00477_8, 2020/04
Pshenichnikov, A.; Kurata, Masaki; Nagae, Yuji
Dai-24-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (USB Flash Drive), 4 Pages, 2019/06
Pshenichnikov, A.; Yamazaki, Saishun; Bottomley, D.; Nagae, Yuji; Kurata, Masaki
Journal of Nuclear Science and Technology, 56(5), p.440 - 453, 2019/05
Times Cited Count:13 Percentile:85.03(Nuclear Science & Technology)Pshenichnikov, A.; Yamazaki, Saishun; Nagae, Yuji; Kurata, Masaki
Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 8 Pages, 2019/05
Pshenichnikov, A.; Kurata, Masaki; Nagae, Yuji; Yamazaki, Saishun
Proceedings of International Topical Workshop on Fukushima Decommissioning Research (FDR 2019) (Internet), 4 Pages, 2019/05
Yamazaki, Saishun; Pshenichnikov, A.; Pham, V. H.; Nagae, Yuji; Kurata, Masaki; Tokushima, Kazuyuki*; Aomi, Masaki*; Sakamoto, Kan*
Proceedings of Annual Topical Meeting on Reactor Fuel Performance (TopFuel 2018) (Internet), 8 Pages, 2018/10
It is predictively evaluated that degradation of fuel assembly proceeded in a certain steam-starved condition at the early stage of a SA at 1F unit 2 (BWR). As for PWR fuel assembly, effective steam flow rate was properly indicated by normalizing to a unit of g-HO/sec/rod which is used as an important parameter for evaluating fuel degradation progression. Due to the inhomogeneous configuration of BWR fuel assembly, the difference of Zry oxidation and hydrogen uptake between the inside and outside of the channel box cannot be properly evaluated by this normalization. Instead of g-HO/sec/rod, proper evaluation unit for BWR configuration is necessary. To accumulate Zry oxidation and hydrogen uptake data for steam-starved conditions, high temperature oxidation tests were performed using a simulated BWR fuel bundle sample. The use of equivalent diameter of the cross section of BWR fuel assembly was proposed for normalization of effective steam flow rate.
Pshenichnikov, A.; Yamazaki, Saishun; Nagae, Yuji; Kurata, Masaki
no journal, ,
Nagae, Yuji; Shibata, Hiroki; Pshenichnikov, A.; Yamazaki, Saishun; Kurata, Masaki
no journal, ,
Pshenichnikov, A.; Yamazaki, Saishun; Nagae, Yuji; Kurata, Masaki
no journal, ,
Yamazaki, Saishun; Pshenichnikov, A.; Pham, V. H.; Nagae, Yuji; Kurata, Masaki
no journal, ,
no abstracts in English
Yamazaki, Saishun; Pshenichnikov, A.; Nagae, Yuji; Kurata, Masaki; Sakamoto, Kan*; Tokushima, Kazuyuki*; Aomi, Masaki*
no journal, ,
no abstracts in English
Pshenichnikov, A.; Yamazaki, Saishun; Nagae, Yuji; Kurata, Masaki
no journal, ,