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Sato, Junya; Kikuchi, Hiroshi*; Kato, Jun; Sakakibara, Tetsuro; Matsushima, Ryotatsu; Sato, Fuminori; Kojima, Junji; Nakazawa, Osamu
QST-M-8; QST Takasaki Annual Report 2016, P. 62, 2018/03
no abstracts in English
Sato, Junya; Suzuki, Shinji*; Kato, Jun; Sakakibara, Tetsuro; Meguro, Yoshihiro; Nakazawa, Osamu
QST-M-2; QST Takasaki Annual Report 2015, P. 87, 2017/03
no abstracts in English
Sato, Junya; Suzuki, Shinji*; Kato, Jun; Sakakibara, Tetsuro; Meguro, Yoshihiro; Nakazawa, Osamu
QST-M-2; QST Takasaki Annual Report 2015, P. 88, 2017/03
no abstracts in English
Meguro, Yoshihiro; Nakagawa, Akinori; Kato, Jun; Sato, Junya; Nakazawa, Osamu; Ashida, Takashi
Proceedings of International Conference on the Safety of Radioactive Waste Management (Internet), p.139_1 - 139_4, 2016/11
A variety of radioactive wastes have been generated in decommissioning of Fukushima Daiichi Nuclear Power Station. It is necessary to evaluate feasibility of conditioning methods to these wastes, because the majority of such wastes have not been solidified in Japan. The authors investigated an approach for screening of conditioning methods for the Fukushima wastes on the basis of the findings of the existing methods and results of fundamental solidification tests using synthetic Fukushima wastes. Here five solidification methods were selected, and also 13 wastes with different chemical composition are solidified, and characteristics of the solidified form are studied. A screening flow was proposed, and evaluation criteria on each step in the flow was set up. In this presentation a trial result was opened for a waste and improvements of the screening flow found in the trial evaluation was described.
Nakayama, Takuya; Suzuki, Shinji; Hanada, Keiji; Tomioka, Osamu; Sato, Junya; Irisawa, Keita; Kato, Jun; Kawato, Yoshimi; Meguro, Yoshihiro
Proceedings of 2nd International Symposium on Cement-based Materials for Nuclear Wastes (NUWCEM 2014) (CD-ROM), 12 Pages, 2014/06
Okada, Takashi; Uematsu, S.; Tobita, Noriyuki; Kato, Junya
9th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM '03), 0 Pages, 2003/00
None
Kato, Junya; Miyauchi, Atsushi; Yamasaki, Akito*
no journal, ,
no abstracts in English
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.
Miura, Akihiko; Kato, Junya; Yamashita, Teruo; Shiotsuki, Masao; Matsumoto, Shiro*
no journal, ,
no abstracts in English
Kato, Junya; Miura, Akihiko; Shiotsuki, Masao; Yamashita, Teruo
no journal, ,
To examine long-life vitrification melter, static corrosion tests of electrode materials are conducted to measure corrosion rate. Samples taken from the tests are observed and analyzed using SEM/EDX. As a result, NCF690 and RS311 which are the nickel based alloy show the high corrosion resistance in molten glass because high dense CrO layer is observed at the glass contact surface.
Kato, Junya; Miura, Akihiko; Yamashita, Teruo; Shiotsuki, Masao
no journal, ,
no abstracts in English
Takaya, Akikazu; Kato, Junya; Fujiwara, Koji; Ueno, Tsutomu
no journal, ,
no abstracts in English
Kato, Junya; Takaya, Akikazu; Fujiwara, Koji; Isozaki, Koei
no journal, ,
no abstracts in English
Nakazaki, Katsutoshi; Takaya, Akikazu; Kato, Junya; Kobayashi, Masahiro; Matsumura, Tadayuki; Niitsuma, Koichi; Fujiwara, Koji
no journal, ,
no abstracts in English
Kato, Junya; Nakazaki, Katsutoshi; Takaya, Akikazu; Matsumura, Tadayuki; Niitsuma, Koichi; Kodaka, Akira; Fujiwara, Koji
no journal, ,
no abstracts in English
Sato, Junya; Suzuki, Shinji; Nakagawa, Akinori; Kato, Jun; Sakakibara, Tetsuro; Nakazawa, Osamu; Yamashita, Masaaki; Sato, Fuminori; Sukegawa, Hirobumi; Meguro, Yoshihiro
no journal, ,
no abstracts in English
Sato, Junya; Suzuki, Shinji; Nakagawa, Akinori; Kato, Jun; Sakakibara, Tetsuro; Meguro, Yoshihiro; Nakazawa, Osamu
no journal, ,
no abstracts in English
Sato, Junya; Suzuki, Shinji; Nakagawa, Akinori; Kato, Jun; Sakakibara, Tetsuro; Meguro, Yoshihiro; Nakazawa, Osamu
no journal, ,
no abstracts in English
Meguro, Yoshihiro; Sato, Junya; Kato, Jun; Nakagawa, Akinori; Koma, Yoshikazu; Ashida, Takashi
no journal, ,
A large quantity of contaminated water is accumulated in nuclear reactor buildings in Fukushima Daiichi Nuclear Power Station. Because various radionuclides are dissolved in the accumulated water, several decontamination devices based on deposition and adsorption are used for the decontamination. Therefore, several sludge and used adsorption materials are generated. These most are different from wastes caused by the operation of commercial nuclear power stations so far in properties, and these have not been disposed of commercially. As then feasibility of conventional solidification techniques to the wastes should be investigated prior to selection of solidification technique of the wastes. In this study as a first step of feasibility study, three types of sludge and three absorbents were solidified using cement materials and solidification behavior and properties of solidified material were investigated, and then feasibility of cementation to these wastes was evaluated.