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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).

Oral presentation

Oral presentation

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant, 13; Full-scale experiment of cement based encapsulation

Yamashita, Masaaki; Sato, Fuminori; Horiguchi, Kenichi; Kojima, Junji; Sakai, Etsuo*; Atarashi, Daiki*; Kadota, Hirofumi*

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

A Basic study for the low-level radioactive liquid solidification by using geopolymer method

Kadota, Hirofumi*; Atarashi, Daiki*; Sakai, Etsuo*; Horiguchi, Kenichi

no journal, , 

no abstracts in English

Oral presentation

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant 12; Small-scale experiment of cement based encapsulation

Horiguchi, Kenichi; Sato, Fuminori; Yamashita, Masaaki; Kojima, Junji; Kadota, Hirofumi*; Atarashi, Daiki*; Sakai, Etsuo*

no journal, , 

A large amount of nitrate in effluent occurring from Tokai reprocessing plant might cause environmental pollution. The effluent is planning to be encapsulated by cement after treated in the nitrate ion decomposition process. In this presentation, we will report the results of the small scale tests for cement solidification technology development of effluent containing a sodium carbonate.

Oral presentation

Development of treatment for low radioactive waste in Tokai Reprocessing Plant, 23; Study on the effect of impurities present in waste liquid on cement solidification

Matsushima, Ryotatsu; Takano, Masato; Atarashi, Daiki*; Saito, Yasuo

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

Development of treatment for low radioactive waste in Tokai Reprocessing Plant, 28-2; Study on the effect of impurities present in waste liquid on cement solidification

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.

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