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Tokai Reprocessing Technology Development Center
JAEA-Evaluation 2015-012, 83 Pages, 2015/12
JAEA-Evaluation-2015-012.pdf:6.67MB
Japan Atomic Energy Agency (hereafter referred as "JAEA") consulted the "Evaluation Committee of Research and Development Activities for Fast Reactor Cycle" to assess the issue on "Research and Development on Reprocessing of Nuclear Fuel Materials" conducted by JAEA during the period from FY2010 to FY2014. In response to the JAEA's request, the committee assessed the R&D programs and the activities of JAEA related to the issue and concluded the mission was accomplished. This evaluation was performed based on the "General guideline for the evaluation of government R&D activities", the "Guideline for evaluation of R&D in Ministry of Education, Culture, Sports, Science and Technology (MEXT)" and the "Operational rule for evaluation of R&D activities" by JAEA.
Aoshima, Atsushi; Ueno, Tsutomu; Shiotsuki, Masao
Proceedings of 16th International Conference on Nuclear Engineering (ICONE-16) (CD-ROM), 9 Pages, 2008/05
In TVF, concentrated high radioactive liquid waste produced in TRP has been vitrified since 1995. Because of very corrosive condition of melting glass, design life of a melter is limited five years and it requires interruption of plant operation and generation of high radioactive solid waste for melter change. To improve this situation, prolongation of melter design life time by increasing corrosion resistance of structural material is required strongly. Effective removal of noble metal from a melter is also required because accumulated noble metal cause shortening lifetime of a melter. So, JAEA tried to develop a melter which equipped with ability of high corrosion resistance and control temperature distribution for noble metal easy drain out. Mechanical removal technology of remained noble metal rich glass also used if necessary. Low temperature glassing technology and advance removal of noble metal from concentrated high radioactive liquid are also be studying.
Aoshima, Atsushi; Ueno, Tsutomu; Shiotsuki, Masao
Proceedings of European Nuclear Conference 2007 (ENC 2007) (CD-ROM), 5 Pages, 2007/09
Tokai Vitrification Facility (TVF) started hot operation in 1996 and produced 241 canisters as of June 2007. Through TVF operation, JAEA had much experience and accumulated much technical know-how which indicated that management for noble metal accumulation in a melter was key technology for smooth plant operation. JAEA should continue service operation based on a vitrification contract with the Japanese utilities because there remains about two third of High Active Liquid Waste (HALW) produced in the reprocessing service operation of Tokai Reprocessing Plant (TRP). TVF melter is designed in condition of five years life time because of very corrosive characteristic of melted glass. Five years design life time is equivalent to 500 canisters production in TVF. Because estimated number of canisters which will be produced in the future is over 500 canisters, exchange of the present melter is necessary. From these situations, JAEA decided basic strategy to increase stability of the existing melter operation and develop an advanced new melter for replacement in future which has largely prolonged life time and high noble metal drain ability. To attain these targets, JAEA extracted necessary key technologies to assemble into a ten years road map and started development. This development has been progressing on schedule.
Nakatani, Takayoshi; Kozaka, Tetsuo; Niitsuma, Koichi; Fujiwara, Koji; Semba, Yasunari; Abe, Shinya
no journal, ,
no abstracts in English
Yamashita, Teruo; Miura, Akihiko; Kato, Junya; Shiotsuki, Masao; Ono, Isamu*; Fukui, Toshiki*; Yamasaki, Akito*; Matsumoto, Shiro*
no journal, ,
The objective of this development is to extend vitrification melter life-time to reduce burden of the high level radioactive waste management by applying advanced technologies. The candidate concepts of the long-life melter were studied with evaluation of adopted important advanced technologies such as skull layer conditions and the commutative electrode structure. It was concluded that such technology has a potential to extend melter life as 20 years even in the preliminary studies. Based on the obtained results, after the following fiscal year, evaluation of each component, small scale melter examination, and development and evaluation of simulation tool are carried out.
Miura, Akihiko; Nakajima, Masayoshi; Yamashita, Teruo; Sakai, Takaaki; Shiotsuki, Masao; Sato, Akihiro*; Kawahara, Hitoshi*
no journal, ,
no abstracts in English
Miura, Akihiko; Kato, Junya; Yamashita, Teruo; Shiotsuki, Masao; Matsumoto, Shiro*
no journal, ,
no abstracts in English
Kobayashi, Hidekazu; Sasage, Kenichi; Usui, Yasufumi; Ayame, Yasuo; Shiotsuki, Masao
no journal, ,
no abstracts in English
Sato, Hideo; Kurosawa, Akira; Nagaishi, Ryuji; Yamada, Reiji; Watahiki, Masaru
no journal, ,
no abstracts in English
Kato, Junya; Miura, Akihiko; Shiotsuki, Masao; Yamashita, Teruo
no journal, ,
To examine long-life vitrification melter, static corrosion tests of electrode materials are conducted to measure corrosion rate. Samples taken from the tests are observed and analyzed using SEM/EDX. As a result, NCF690 and RS311 which are the nickel based alloy show the high corrosion resistance in molten glass because high dense CrO
layer is observed at the glass contact surface.
Yamashita, Teruo; Masaki, Toshio; Shiotsuki, Masao; Yamasaki, Akito*; Ito, Toshiyuki*; Ono, Isamu*; Matsumoto, Shiro*
no journal, ,
no abstracts in English
Miyauchi, Atsushi; Morikawa, Yo; Sasage, Kenichi; Yamashita, Teruo; Shiotsuki, Masao
no journal, ,
no abstracts in English
Sasage, Kenichi; Miyauchi, Atsushi; Morikawa, Yo; Yamashita, Teruo; Shiotsuki, Masao
no journal, ,
Viscosity and specific resistivity of simulated waste glass was measured to investigate characterization of waste glass processed by the long-life vitrification melter. The composition of the simulated waste glass was varied based on 8 cases of assumed spent fuel conditions and reprocessing flows including reprocessing of FBR fuel with minor actinides separation. The viscosity of the sample glasses was from 0.5 to 1.8 times that of waste glass with standard composition. The specific resistivity of the sample glasses was from 0.5 to 1.5 times that of standard waste glass.
Nakajima, Masayoshi; Oeda, Mikihiro; Yamashita, Teruo; Shiotsuki, Masao; Kawahara, Hitoshi*; Sato, Akihiro*
no journal, ,
no abstracts in English
Ito, Yoshiyuki; Ikegami, Yasushi; Suda, Masanori; Shimbara, Shigehiro; Fujiwara, Koji
no journal, ,
The off gas from the TVF glass melter was washed by the scrubber and the Venturi Scrubber, but boric acid in the off gas was put on the pipe of the off gas scrubber. Differential presser of the Venturi Scrubber was increased by the vitrification process. The mechanism was investigated, therefore the spray from the scrubber was sent up to the off gas line, the spray was dried with the vitrification cell air, because the vitrification cell air was low humidity, the humidity is 15 percent. And the boric acid in the spray was extracted, and the extraction was carried to the entrance of the venturi scrubber. And also, by the check experiment of the washing method, it was confirmed that the confluence line of vitrification cell air was effectively washed.
Sato, Hideo; Kurosawa, Akira; Nagaishi, Ryuji; Yamada, Reiji; Watahiki, Masaru
no journal, ,
no abstracts in English
Kato, Junya; Miura, Akihiko; Yamashita, Teruo; Shiotsuki, Masao
no journal, ,
no abstracts in English
Miura, Akihiko; Kobayashi, Hidekazu; Ayame, Yasuo; Shiotsuki, Masao; Weisenburger, S.*; Roth, G.*
no journal, ,
no abstracts in English
Fujiwara, Koji
no journal, ,
no abstracts in English
Nagaishi, Ryuji; Yamada, Reiji; Sato, Hideo; Kurosawa, Akira; Watahiki, Masaru; Hiyama, Toshiaki
no journal, ,
Radioactive glass wastes, which emit ionizing radiations and heats, are discharged from nuclear power reactor, and are now kept air-cooling at the stage of interim storage. They are expected to be utilized as useful materials or energy resources in the future. In the present study, radiation-induced reactions were investigated by using the analytical pieces of glass wastes at Tokai Reprocessing Plant (TRP), JAEA. Influences of 
or beta rays on reactions of metal ions in aqueous solution were measured, and the feasibility of wastes as a radiation source was also discussed.