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Morita, Kenji; Morimoto, Makoto; Hisada, Masaki; Fukui, Yasutaka
JAEA-Technology 2015-038, 30 Pages, 2016/02
JAEA-Technology-2015-038.pdf:14.65MB
The Old Waste Treatment Facility for JOYO (Old JWTF) has been operated to treat radioactive liquid waste from the experimental fast reactor JOYO and post irradiation examination facilities. Operation of Old JWTF stopped in 1995, and dismantling & decontamination method has discussed. As a response to discussion results of remote and dismantling method in high dose environment on 2013, its concept examination was discussed on 2014. Results are follows. As a cutting tool for Old JWTF equipment, wire saw is selected from cutting ability (speed and thickness of objects). Discussed the component technology of wire saw remote operation system (handling, monitoring, collection method of secondary waste, else).
Morita, Kenji; Morimoto, Makoto; Hisada, Masaki; Fukui, Yasutaka
JAEA-Technology 2015-037, 28 Pages, 2016/01
JAEA-Technology-2015-037.pdf:8.44MB
Deuterium Critical Assembly (DCA) achieved first critically in 1969 and used for research and development program of Advanced Thermal Reactor. To achieved the aim of facility, DCA decommissioning work started in 2002. Decommissioning schedule consists of 4 stages. The third stage, which is the main work (To dismantle and remove reactor vessel and main equipment), was started in 2008 and will be finished at 2023. This report describes DCA decommissioning work and data (Ability of cutting tools and Man-hours) in 2013.
SiYoshida, Rikiya*; Fukui, Masaki*; Haga, Yoshinori; Yamamoto, Etsuji; Onuki, Yoshichika; Okawa, Mario*; Malaeb, W.*; Shin, S.*; Muraoka, Yuji*; Yokoya, Takayoshi*
Physical Review B, 85(24), p.241102_1 - 241102_4, 2012/06
Times Cited Count：18 Percentile：59.41(Materials Science, Multidisciplinary)Hirokawa, Katsunori; Hisada, Masaki; Fukui, Yasutaka; Inoue, Setsunari
Dekomisshoningu Giho, (44), p.33 - 42, 2011/09
In Japan Atomic Energy Agency, facilities where the mission was finished and superannuation facilities are decommissioned systematically for rationalization and efficiency improvement of business. It is necessary to execute safe and economically by making good use of the technology according to the kind of facilities and the feature of the dismantlement object. In this report, it reports on the radiation measurement, decontamination and dismantling technology that develops in the Waste Treatment Technology Section O-ARAI Research and Development Center JAEA.
Rh
)Si studied by laser angle-resolved photoemission spectroscopyYoshida, Rikiya*; Nakamura, Yoshiaki*; Fukui, Masaki*; Haga, Yoshinori; Yamamoto, Etsuji; Onuki, Yoshichika; Okawa, Mario*; Shin, S.*; Hirai, Masaaki*; Muraoka, Yuji*; et al.
Journal of Physics; Conference Series, 273, p.012021_1 - 012021_4, 2011/02
Times Cited Count：1 Percentile：33.9(Physics, Condensed Matter)SiYoshida, Rikiya*; Nakamura, Yoshiaki*; Fukui, Masaki*; Haga, Yoshinori; Yamamoto, Etsuji; Onuki, Yoshichika; Okawa, Mario*; Shin, S.*; Hirai, Masaaki*; Muraoka, Yuji*; et al.
Physical Review B, 82(20), p.205108_1 - 205108_6, 2010/11
Times Cited Count：62 Percentile：88.1(Materials Science, Multidisciplinary)Kato, Junya; Miyauchi, Atsushi; Aoshima, Atsushi; Shiotsuki, Masao; Yamashita, Teruo; Nakajima, Masayoshi; Morikawa, Yo; Miura, Akihiko; Fukui, Toshiki*; Yamasaki, Akito*; et al.
no journal, ,
no abstracts in English
Yamashita, Teruo; Miura, Akihiko; Kato, Junya; Shiotsuki, Masao; Ono, Isamu*; Fukui, Toshiki*; Yamasaki, Akito*; Matsumoto, Shiro*
no journal, ,
The objective of this development is to extend vitrification melter life-time to reduce burden of the high level radioactive waste management by applying advanced technologies. The candidate concepts of the long-life melter were studied with evaluation of adopted important advanced technologies such as skull layer conditions and the commutative electrode structure. It was concluded that such technology has a potential to extend melter life as 20 years even in the preliminary studies. Based on the obtained results, after the following fiscal year, evaluation of each component, small scale melter examination, and development and evaluation of simulation tool are carried out.
Yamasaki, Satoshi*; Fukui, Kazuhiko*; Kono, Hidetoshi; Shimizu, Kentaro*; Sarai, Akinori*; Terada, Toru*
no journal, ,
