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Tsuji, Tomoyuki; Sugitsue, Noritake; Sato, Fuminori; Matsushima, Ryotatsu; Kataoka, Shoji; Okada, Shota; Sasaki, Toshiki; Inoue, Junya
Nihon Genshiryoku Gakkai-Shi ATOMO
, 62(11), p.658 - 663, 2020/11
no abstracts in English
Sato, Fuminori; Matsushima, Ryotatsu; Ito, Yoshiyuki
QST-M-16; QST Takasaki Annual Report 2017, P. 60, 2019/03
Hydrogen gas generation by 
-radiation from cement solidified products loading low-level radioactive liquid waste generated at LWTF in Tokai Reprocessing Facility was studied.
Matsushima, Ryotatsu; Sato, Fuminori; Saito, Yasuo; Atarashi, Daiki*
Proceedings of 3rd International Symposium on Cement-based Materials for Nuclear Wastes (NUWCEM 2018) (USB Flash Drive), 4 Pages, 2018/10
At TRP, LWTF was constructed as a facility for processing low radioactive liquid waste and solid waste generated at TRP, and a cold test is been carrying out. In this facility, initially, nitrate waste liquid after separation of nuclides generated with treatment of low radioactive liquid waste was to be solidified by using borate. However, at present, it is necessary to decompose the nitrate in the liquid waste to reduce the environmental burden. For the reason, as a plan to replace the nitrate with the carbonate and to make it as a cement based encapsulation, we are studying for the introduction of the facility. Currently, as a cement solidification technology development for this liquid waste, we are studying the application of cement material based on blast furnace slag (BFS) as a main component. In this report, we show the results of the test conducted on the actual scale (200 L drum can scale).
Ito, Yoshiyuki; Matsushima, Ryotatsu; Sato, Fuminori
QST-M-8; QST Takasaki Annual Report 2016, P. 69, 2018/03
no abstracts in English
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
Matsushima, Ryotatsu*; Arai, Tsuyoshi*; Saito, Akihito*; Horiguchi, Kenichi; Sugaya, Atsushi
no journal, ,
no abstracts in English
Matsushima, Ryotatsu*; Arai, Tsuyoshi*; Horiguchi, Kenichi; Sugaya, Atsushi
no journal, ,
A mass of radioactive polluted water that arisen from the Accident at Fukushima Nuclear Power Stations is just stored on the sites. We presume the polluted water contains sodium chloride and boric acid; therefore, developments of new immobilization matrices suitable for these chemicals are required. In this study, it was focused attention on borate glass based immobilization with the use of boric acid in the polluted water. In our previous work, it was confirmed that a borate glass is formed when boric acid and sodium chloride powder were used in a molar ratio 1:0.5 and they were melted at 1100
C for three hours. A borate glass will be formed if chlorine is volatilized from the glass. In this time, we studied on thermal behaviors during forming a glass to make sure that chlorine is volatilized from the glass.
Matsushima, Ryotatsu; Ito, Yoshiyuki; Kojima, Junji; Masuzawa, Shun*; Arai, Tsuyoshi*
no journal, ,
no abstracts in English
Matsushima, Ryotatsu; Sato, Fuminori; Horiguchi, Kenichi; Kojima, Junji; Yamashita, Masaaki*; Sakai, Etsuo*; Atarashi, Daiki*
no journal, ,
no abstracts in English
Ito, Yoshiyuki; Matsushima, Ryotatsu; Sato, Fuminori; Kojima, Junji
no journal, ,
no abstracts in English
Ito, Yoshiyuki; Matsushima, Ryotatsu; Sato, Fuminori; Saito, Yasuo
no journal, ,
no abstracts in English
Matsushima, Ryotatsu; Sato, Fuminori; Saito, Yasuo; Atarashi, Daiki*
no journal, ,
The Low Radioactive Waste Treatment Technology Development Facility (LWTF) of the Tokai Reprocessing Facility was constructed as a facility for processing low radioactive liquid waste and solid waste generated from the reprocessing facility, and cold tests are being conducted. In this facility, nitrate waste liquor generated with the treatment of liquid waste was made solidified by using borate, but now it is planned to replace it with carbonate waste liquid and then to make cement solidified body. It is studying and designing for equipment introduction. In this report, we investigated the influence of strength and waste composition on change of cement solidified body over time by carrying out cement kneading / solidification test on this carbonate waste liquid on a real scale (200 L drum) will be reported.
-ray irradiation for cement-solidified products of used adsorbents for water decontaminationSato, Junya; Kikuchi, Hiroshi*; Kato, Jun; Sakakibara, Tetsuro; Matsushima, Ryotatsu; Sato, Fuminori; Kojima, Junji; Nakazawa, Osamu
no journal, ,
no abstracts in English
Ito, Yoshiyuki; Matsushima, Ryotatsu; Sato, Fuminori; Hashimoto, Takanori*; Suzuki, Tatsuya*; Miyabe, Shinsuke*; Sakuma, Takashi*; Kikuchi, Kaoru*; Izumi, Takeshi*
no journal, ,
no abstracts in English
Sato, Fuminori; Matsushima, Ryotatsu; Ito, Yoshiyuki; Saito, Yasuo
no journal, ,
no abstracts in English
Matsushima, Ryotatsu; Sato, Fuminori; Saito, Yasuo; Atarashi, Daiki*
no journal, ,
no abstracts in English
Sato, Fuminori; Matsushima, Ryotatsu; Ito, Yoshiyuki; Saito, Yasuo
no journal, ,
no abstracts in English
Ito, Yoshiyuki; Matsushima, Ryotatsu; Takano, Masato; Suzuki, Tatsuya*; Miyabe, Shinsuke*; Sakuma, Takashi*
no journal, ,
no abstracts in English
SmYoshida, Masaaki*; Arai, Tsuyoshi*; Matsushima, Ryotatsu; Saito, Yasuo
no journal, ,
no abstracts in English
Kida, Fukuka*; Nakamura, Fumiya*; Arai, Tsuyoshi*; Matsushima, Ryotatsu; Saito, Yasuo
no journal, ,
no abstracts in English
