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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
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
Matsushima, Ryotatsu; Takano, Masato; Atarashi, Daiki*; Saito, Yasuo
no journal, ,
no abstracts in English
Takahashi, Kiyofumi; Matsushima, Ryotatsu; Sato, Fuminori; Saito, Yasuo
no journal, ,
no abstracts in English
Sato, Fuminori; Kataoka, Shoji; Matsushima, Ryotatsu; Terunuma, Tomomi
no journal, ,
no abstracts in English
Kataoka, Shoji; Matsushima, Ryotatsu; Sato, Fuminori; Terunuma, Tomomi
no journal, ,
The Low-Level Radioactive Waste Treatment Technology Development Facility (LWTF) of Tokai Reprocessing Facility has been 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, the nitrate waste liquid generated by the treatment of liquid waste was decided to be solidified using borate, but now it is planned to replace it with carbonate waste liquid and then make it cement solid. Therefore, we are proceeding with examination and design for the introduction of equipment. In this report, we conduct a cement kneading and solidification test on a carbonate waste liquid on a real scale (200L drum), and report on the results of examining the influence of the cement solidified body over time and the strength when the waste liquid composition changes.
Kataoka, Shoji; Tsunoda, Hiroki; Matsushima, Ryotatsu; Sato, Fuminori; Shirozu, Hidetomo
no journal, ,
Low Active Waste Treatment Development Facility (LWTF) in Tokai Reprocessing Plant (TRP) is a facility for treatment of low-radioactive liquid and solid wastes generated from the TRP. The liquid wastes treated in LWTF are concentrated low-radioactive liquid waste and phosphoric acid solution, and they are planned to be solidified with cement in our new equipment. The concentrated liquid wastes are separated into slurry and carbonate compounds by a nuclide separation equipment currently in LWTF and a nitrate decomposition equipment which is under development, and then the cement solidification will be carried out on each liquid waste. Currently, studying and designing for the introduction of the nitrate decomposition equipment and cement solidification equipment is in progress. In this paper, results of the cementation demonstration on simulated waste liquids of the carbonate, phosphoric acid and slurry are reported.
Matsushima, Ryotatsu; Ito, Yoshiyuki; Kojima, Junji; Masuzawa, Shun*; Arai, Tsuyoshi*
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.
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
Matsushima, Ryotatsu; Takahashi, Kiyofumi; Saito, Yasuo; Kikuchi, Yukihiro*; Atarashi, Daiki*; Shirozu, Hidetomo
no journal, ,
Low Active Waste Treatment Development Facility (LWTF) is planning to solidify the cement waste liquid generated at the Tokai Reprocessing Facility. In the previous report, it has been shown that the carbonate waste liquid can be solidified by conducting a solidification test on the waste liquid simulating the carbonate waste liquid containing sodium carbonate and sodium nitrate. On the other hand, it is expected that sodium sulfate will coexist as a foreign substances in the carbonate waste liquid, even though it is a trace amount, and it has been confirmed that there is no effect of sodium sulfate coexists in beaker-scale test. In this report, a actual-scale test is carried out, confirm that there is no effect when sodium sulfate coexists, and the results is reported. It was confirmed that the presence or absence of sodium sulfate in the waste liquid had no effect on the fluidity of the sample after kneading, the compressive strength of the sample after curing, etc., and thus had no effect on the solidified body properties.
Sato, Fuminori; Kataoka, Shoji; Matsushima, Ryotatsu; Otake, Katsumi*; Shirozu, Hidetomo
no journal, ,
no abstracts in English
Sato, Fuminori; Kataoka, Shoji; Matsushima, Ryotatsu; Otake, Katsumi*; Shirozu, Hidetomo
no journal, ,
no abstracts in English
