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Abe, Yuta; Yamashita, Takuya; Sato, Ikken; Nakagiri, Toshio; Ishimi, Akihiro
Journal of Nuclear Engineering and Radiation Science, 6(2), p.021113_1 - 021113_9, 2020/04
Abe, Yuta; Yamashita, Takuya; Sato, Ikken; Nakagiri, Toshio; Ishimi, Akihiro; Nagae, Yuji
Proceedings of 26th International Conference on Nuclear Engineering (ICONE-26) (Internet), 9 Pages, 2018/07
Maruyama, Shinichiro*; Watatani, Satoshi*
Mitsui Sumitomo Kensetsu Gijutsu Kenkyu Kaihatsu Hokoku, (15), p.107 - 112, 2017/10
It is essential to estimate characteristics and forms of fuel debris for safe and reliable removing at the decommissioning of the Fukushima Daiichi Nuclear Power Plant (1F). For the estimation, melting behavior of fuel assembly in the accident is being researched. To proceed the research, the fuel debris were need to cut, and the abrasive water jet (AWJ) which had enough results for cutting ceramic material or mixed material of zirconium alloy and stainless. The test results demonstrated that AWJ could cut the fuel assembly and accumulated the cutting data which will be subservient when removing the fuel debris in future.
Abe, Yuta; Sato, Ikken; Nakagiri, Toshio; Ishimi, Akihiro; Nagae, Yuji
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 7 Pages, 2017/04
Abe, Yuta; Sato, Ikken; Ishimi, Akihiro; Nakagiri, Toshio; Nagae, Yuji
Proceedings of 24th International Conference on Nuclear Engineering (ICONE-24) (DVD-ROM), 7 Pages, 2016/06
A new experimental program using non-transfer type plasma heating is under consideration in JAEA to clarify the uncertainty on core-material relocation (CMR) behavior of BWR. In order to confirm the applicability of this new technology, authors performed preparatory plasma heating tests using small-scale test pieces (107 mm 107 mm
222 mmh). Based on these preliminary results, an excellent perspective in terms of applicability of the non-transfer plasma heating technology to the SA (Severe Accident) experimental study was obtained. Furthermore, JAEA is preparing for the next step intermediate-scale preparatory tests in 2016 using ca. 50 rods and a control blade that would not only confirm its technical applicability, but also some insights relevant to the issue on CMR itself.
Yamane, Tsuyoshi; Akino, Fujiyoshi;
PHYSOR 96: Int. Conf. on the Physics of Reactors, 2, p.E290 - E299, 1996/00
no abstracts in English
; Akino, Fujiyoshi; Yamane, Tsuyoshi; ; Kitadate, Kenji; ; Takeuchi, Motoyoshi; Ono, Toshihiko; Kaneko, Yoshihiko
JAERI 1305, 138 Pages, 1987/08
no abstracts in English
; ; ; Iwamoto, K.
JAERI-M 86-046, 17 Pages, 1986/03
no abstracts in English
Sato, Ikken; Nakagiri, Toshio; Abe, Yuta; Ishimi, Akihiro; Nagae, Yuji
no journal, ,
An experimental program using non-transfer type plasma heating is underway in JAEA in order to address large uncertainty in core-material-relocation behavior in severe accidents of BWRs. Based on preparatory tests, two experiments with simulated fuel rods, channel box, control blade and lower support structure were carried out. After the heating, control blade and channel box were mostly gone but major part of the fuel columns remained standing. Downward relocation of molten materials probably consisting mainly of metals was confirmed in the lower support structure region. These results together with data from planned X-ray CT measurement on the heat teat pieces will provide effective data for core material relocation behavior with the BWR design conditions.
Sato, Ikken; Nakagiri, Toshio; Abe, Yuta; Ishimi, Akihiro; Nagae, Yuji
no journal, ,
An experimental program using non-transfer type plasma heating is underway in JAEA in order to address large uncertainty in core-material-relocation behavior in severe accidents of BWRs. Based on preparatory tests, an experiment with simulated fuel rods, channel box, control blade and lower support structure was carried out. After the heating, control blade and channel box were mostly gone but major part of the fuel columns remained standing. Downward relocation of molten materials probably consisting mainly of metals was confirmed in the lower support structure region. These results together with data from planned X-ray CT measurement on the heat teat piece will provide effective data for core material relocation behavior with the BWR design conditions.
Abe, Yuta; Nakagiri, Toshio; Sato, Ikken; Nakano, Natsuko*; Yamaguchi, Hidenobu*
no journal, ,
no abstracts in English
Kawakami, Tomohiko*; Abe, Yuta; Spaziani, F.*; Nakano, Natsuko*; Nakagiri, Toshio
no journal, ,
no abstracts in English
Abe, Yuta; Nakagiri, Toshio; Sato, Ikken; Nakano, Natsuko*; Yamaguchi, Hidenobu*; Maruyama, Shinichiro*
no journal, ,
no abstracts in English
Abe, Yuta; Nakagiri, Toshio; Sato, Ikken; Nakano, Natsuko*; Tanaka, Hiroshi*; Yamaguchi, Hidenobu*
no journal, ,
no abstracts in English
Maruyama, Shinichiro*; Abe, Yuta; Nakagiri, Toshio; Watatani, Satoshi*; Takashima, Yuji*
no journal, ,
no abstracts in English
Abe, Yuta; Sato, Ikken; Nakagiri, Toshio; Nagae, Yuji; Ishimi, Akihiro
no journal, ,
no abstracts in English
Abe, Yuta; Nakagiri, Toshio; Yamashita, Takuya; Noro, Junji*; Matsushima, Tomohiro*; Kawakami, Tomohiko*
no journal, ,
no abstracts in English
Okazaki, Kodai*; Abe, Yuta; Spaziani, F.*; Nakano, Natsuko*; Kawakami, Tomohiko*
no journal, ,
no abstracts in English
Noro, Junji*; Abe, Yuta; Yamashita, Takuya; Matsushima, Tomohiro*
no journal, ,
no abstracts in English
Kawakami, Tomohiko*; Abe, Yuta; Spaziani, F.*; Nakano, Natsuko*; Nakagiri, Toshio
no journal, ,
no abstracts in English
Sato, Ikken; Abe, Yuta; Nakagiri, Toshio; Nagae, Yuji; Ishimi, Akihiro
no journal, ,
no abstracts in English