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Journal Articles

Frontline of R&D for decommissioning and waste disposal, 1; R&D for processing and disposal of low-level radioactive waste and closure of uranium mine

Tsuji, Tomoyuki; Sugitsue, Noritake; Sato, Fuminori; Matsushima, Ryotatsu; Kataoka, Shoji; Okada, Shota; Sasaki, Toshiki; Inoue, Junya

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 62(11), p.658 - 663, 2020/11

no abstracts in English

Journal Articles

Study on hydrogen generation from cement solidified products loading low-level radioactive liquid wastes at Tokai Reprocessing Plant

Sato, Fuminori; Matsushima, Ryotatsu; Ito, Yoshiyuki

QST-M-16; QST Takasaki Annual Report 2017, P. 60, 2019/03

Hydrogen gas generation by $$gamma$$-radiation from cement solidified products loading low-level radioactive liquid waste generated at LWTF in Tokai Reprocessing Facility was studied.

Journal Articles

Development of cement based encapsulation for low radioactive liquid waste in Tokai Reprocessing Plant

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).

Journal Articles

Study on hydrogen generation from cement solidified products loading low-radioactive liquid wastes at Tokai Reprocessing Plant

Ito, Yoshiyuki; Matsushima, Ryotatsu; Sato, Fuminori

QST-M-8; QST Takasaki Annual Report 2016, P. 69, 2018/03

no abstracts in English

Journal Articles

Investigation of hydrogen gas generation by radiolysis for cement-solidified products of used adsorbents for water decontamination

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

Oral presentation

A Basic study for immobilization of radioactive waste including ocean water by the borate glass

Matsushima, Ryotatsu*; Arai, Tsuyoshi*; Saito, Akihito*; Horiguchi, Kenichi; Sugaya, Atsushi

no journal, , 

no abstracts in English

Oral presentation

A Basic study for immobilization of radioactive polluted water derived from the Accident at Fukushima Nuclear Power Stations of Tokyo Electric Power Company using borate glass

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$$^{circ}$$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.

Oral presentation

Development for analysis method of trace elements in low-level radioactive liquid waste of reprocessing plant using iminodiacetic acid resin

Matsushima, Ryotatsu; Ito, Yoshiyuki; Kojima, Junji; Masuzawa, Shun*; Arai, Tsuyoshi*

no journal, , 

no abstracts in English

Oral presentation

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant, 15 Study of cement based encapsulation in full-scale mixing

Matsushima, Ryotatsu; Sato, Fuminori; Horiguchi, Kenichi; Kojima, Junji; Yamashita, Masaaki*; Sakai, Etsuo*; Atarashi, Daiki*

no journal, , 

no abstracts in English

Oral presentation

Study of hydrogen generation from cement solidified products loading low radioactive liquid waste at Tokai reprocessing plant

Ito, Yoshiyuki; Matsushima, Ryotatsu; Sato, Fuminori; Kojima, Junji

no journal, , 

no abstracts in English

Oral presentation

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant, 16; Study on hydrogen generation from cement solidified products

Ito, Yoshiyuki; Matsushima, Ryotatsu; Sato, Fuminori; Saito, Yasuo

no journal, , 

no abstracts in English

Oral presentation

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant, 17; Study on cement based encapsulation of sodium carbonate liquid waste by full-scale mixing

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.

Oral presentation

Investigation of hydrogen gas generation by $$gamma$$-ray irradiation for cement-solidified products of used adsorbents for water decontamination

Sato, Junya; Kikuchi, Hiroshi*; Kato, Jun; Sakakibara, Tetsuro; Matsushima, Ryotatsu; Sato, Fuminori; Kojima, Junji; Nakazawa, Osamu

no journal, , 

no abstracts in English

Oral presentation

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant, 18; Practical study on Cs and Sr adsorption process in LWTF

Ito, Yoshiyuki; Matsushima, Ryotatsu; Sato, Fuminori; Hashimoto, Takanori*; Suzuki, Tatsuya*; Miyabe, Shinsuke*; Sakuma, Takashi*; Kikuchi, Kaoru*; Izumi, Takeshi*

no journal, , 

no abstracts in English

Oral presentation

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant, 20; Practical study on hydrogen generation from cement solidified products

Sato, Fuminori; Matsushima, Ryotatsu; Ito, Yoshiyuki; Saito, Yasuo

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Study on hydrogen generation from cement solidified products of low radioactive effluent

Sato, Fuminori; Matsushima, Ryotatsu; Ito, Yoshiyuki; Saito, Yasuo

no journal, , 

no abstracts in English

Oral presentation

Development of treatment for low radioactive waste in Tokai Reprocessing Plant, 21; Practical study on Cs and Sr adsorption process in LWTF

Ito, Yoshiyuki; Matsushima, Ryotatsu; Takano, Masato; Suzuki, Tatsuya*; Miyabe, Shinsuke*; Sakuma, Takashi*

no journal, , 

no abstracts in English

Oral presentation

Optimization of chromatography method for an advancement of trace analysis of $$^{151}$$Sm

Yoshida, Masaaki*; Arai, Tsuyoshi*; Matsushima, Ryotatsu; Saito, Yasuo

no journal, , 

no abstracts in English

Oral presentation

Development of composite iminodiacetic acid resin for nuclide recovery from high concentration sodium contaminated radioactive liquid waste

Kida, Fukuka*; Nakamura, Fumiya*; Arai, Tsuyoshi*; Matsushima, Ryotatsu; Saito, Yasuo

no journal, , 

no abstracts in English

27 (Records 1-20 displayed on this page)