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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).
Horiguchi, Kenichi; Sugaya, Atsushi; Saito, Yasuo; Tanaka, Kenji; Akutsu, Shigeru; Hirata, Toshiaki
Proceedings of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP '09) (CD-ROM), p.9411_1 - 9411_9, 2009/05
The low-level radioactive Waste treatment Facility (LWTF) was constructed at the Tokai Reprocessing Plant (TRP) and cold test has been carried out since 2006. The waste which is treated in the LWTF is combustible/incombustible solid waste and liquid waste. In the LWTF, The combustible/incombustible solid waste will be incinerated. The liquid waste will be treated by the radio-nuclides removal process subsequently solidified by cement materials. This report describes the essential technologies of the LWTF and results of R&D work for the nitrate-ion decomposition technology for the liquid waste.
Saito, Yasuo; Takano, Masato; Tanaka, Kenji; Kobayashi, Kentaro; Otani, Yoshikuni
Proceedings of International Symposium on Radiation Safety Management 2007 (ISRSM 2007), p.275 - 280, 2007/11
The Low-radioactive Waste Treatment Facility (LWTF), which aims to provide the safe, efficient and economic treatment and disposal of Low-level Liquid Waste (LLW) generated from LWR spent fuel reprocessing, was constructed at the Tokai Reprocessing Plant (TRP), and a cold test is now being carried out. New treatment processes such as a removal process for radio-nuclides and the ROBE (BORSAURE EINENGUNG ANLAGE) solidification process are being implemented in the LWTF. In order to treat the large amount of sodium nitrate contained in the concentrated LLW with higher safety and economy, R&D work on nitrate-ion decomposition technology using a catalytic reduction method and on the solidification process by cementation is being undertaken. The results of this R&D will be adopted in the LWTF in the near future. This report describes an outline of liquid waste treatment in the LWTF and new treatment technologies for LLW to achieve safe, efficient and economic treatment and disposal.
Saito, Yasuo; ; ;
Proceedings of 8th International Conference on Nuclear Engineering (ICONE-8) (CD-ROM), 0 Pages, 2000/00
None
; Saito, Yasuo; ;
Proceedings of 8th International Conference on Nuclear Engineering (ICONE-8) (CD-ROM), 0 Pages, 2000/00
None
Sugaya, Atsushi; Horiguchi, Kenichi; Saito, Yasuo; Tanaka, Kenji; Akutsu, Shigeru; Hirata, Toshiaki
no journal, ,
The Low-level radioactive Waste Treatment Facility (LWTF) was constructed at the Tokai Reprocessing Plant and cold testing has been performed since 2006. The aims of this facility are to provide safe, effective and economic treatment of the Waste. The wastes treated in the LWTF are combustible and incombustible solid waste and liquid waste. The problem of burning up incombustible waste is to generate chlorine gas which causes corrosion. The incinerator is made of corrosion resistant metal and uses cooling water to prevent corrosion. The radio-nuclides separation process is newly-introduced for low-level radioactive liquid waste to reduce the deep geological disposal cost. A large amount of nitrate in the liquid waste might cause the environmental pollution. Nitrate ion decomposition technology is under development. A cement based encapsulation method to immobilize those liquid wastes has been developed. The results of these R&D work will be adopted in the LWTF in the near future.
Susa, Shunsuke*; Mimura, Hitoshi*; Saito, Yasuo; Ito, Yoshiyuki
no journal, ,
no abstracts in English
irradiationIto, Yoshiyuki; Saito, Yasuo; Susa, Shunsuke*; Mimura, Hitoshi*
no journal, ,
no abstracts in English
Ito, Yoshiyuki; Saito, Yasuo; Susa, Shunsuke*; Mimura, Hitoshi*
no journal, ,
no abstracts in English
Ito, Yoshiyuki; Saito, Yasuo; Shinoda, Yu*; Mimura, Hitoshi*; Matsukura, Minoru*; Ishizaki, Eiji*
no journal, ,
no abstracts in English
Sato, Fuminori; Chaki, Takahito*; Saito, Yasuo; Arai, Tsuyoshi*
no journal, ,
Iron phosphate glass that can use phosphorus in waste liquid as a glass material has been noted as a method for solidifying low level radioactive liquid waste generated from a reprocessing facility. The plan of fused glass solidification of liquid waste containing nuclide contamination was discussed.
Chaki, Takahito*; Arai, Tsuyoshi*; Sato, Fuminori; Saito, Yasuo
no journal, ,
no abstracts in English
Mori, Masahiro*; Chaki, Takahito*; Arai, Tsuyoshi*; Sato, Fuminori; Saito, Yasuo
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.
Mori, Masahiro*; Arai, Tsuyoshi*; Sato, Fuminori; Saito, Yasuo
no journal, ,
no abstracts in English
Sato, Fuminori; Mori, Masahiro*; Arai, Tsuyoshi*; Saito, Yasuo
no journal, ,
The result of fused glass solidification test (waste packing ratio, etc.) using simulated waste liquid includes the tracer components based on analysis results of the radioactive liquid waste are reported.
Mori, Masahiro*; Arai, Tsuyoshi*; Sato, Fuminori; Saito, Yasuo
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