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Kobayashi, Hidekazu; Amamoto, Ippei; Yokozawa, Takuma; Yamashita, Teruo; Nagai, Takayuki; Kitamura, Naoto*; Takebe, Hiromichi*; Mitamura, Naoki*; Tsuzuki, Tatsuya*
Proceedings of the ASME 2013 15th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM2013) (CD-ROM), 6 Pages, 2013/09
no abstracts in English
as the dominant sludge constituent generated from the treatment of water used for cooling the stricken power reactorsAmamoto, Ippei; Kobayashi, Hidekazu; Yokozawa, Takuma; Yamashita, Teruo; Nagai, Takayuki; Kitamura, Naoto*; Takebe, Hiromichi*; Mitamura, Naoki*; Tsuzuki, Tatsuya*
Proceedings of the ASME 2013 15th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM2013) (CD-ROM), 8 Pages, 2013/09
The great amount of water used for cooling the stricken power reactors at Fukushima Dai-ichi has resulted in accumulation of "remaining water". As the remaining water is subsequently contaminated by FPs, etc., it is necessary to decontaminate it in order to reduce the volume of liquid radioactive waste and to reuse it again for cooling the reactors. Various techniques are being applied to remove FP, etc. and to make stable waste forms. One of the methods using the iron phosphate glass as a medium is being developed to stabilize the strontium-bearing sludge whose main component is BaSO. From the results hitherto, the iron phosphate glass is regarded as a potential medium for the target sludge.
Nakajima, Masayoshi; Oeda, Mikihiro; Yamashita, Teruo; Shiotsuki, Masao; Kawahara, Hitoshi*; Sato, Akihiro*
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Yamashita, Teruo; Masaki, Toshio; Nakajima, Masayoshi; Nakazaki, Katsutoshi; Toyoshima, Mikihiro
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Nishihara, Kenji; Oigawa, Hiroyuki; Nakayama, Shinichi; Fujiwara, Takeshi; Kobayashi, Hidekazu; Kano, Shigeru; Sasage, Kenichi; Yamashita, Teruo; Ono, Kiyoshi; Shiotani, Hiroki
no journal, ,
The reduction of the storage facility and repository were evaluated for the cases with or without partitioning of Sr-Cs and transmutation of MA in the advanced FBR fuel cycle with the cost estimation for the storage facilities, transporting and repository. As the result, the transmutation of minor actinides is inevitable for the small repository because the heat generation by 
Am is considerable in FBR. The introduction of partitioning, transmutation and long-term storage enable the very compact layout in the repository like TRU wastes such as hulls and end-pieces of the fuel assembly. The cost for the storage and disposal in this case is much smaller than that in other cases, which mitigates the cost increase by the separation process and transmutor.
Kobayashi, Hidekazu; Kano, Shigeru; Yamashita, Teruo
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no abstracts in English
Miura, Akihiko; Nakajima, Masayoshi; Yamashita, Teruo; Sakai, Takaaki; Shiotsuki, Masao; Sato, Akihiro*; Kawahara, Hitoshi*
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no abstracts in English
Miyauchi, Atsushi; Yamanaka, Atsushi; Morikawa, Yo; Sasage, Kenichi; Yamashita, Teruo
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no abstracts in English
Oeda, Mikihiro; Nakajima, Masayoshi; Miura, Akihiko; Yamashita, Teruo; Shiotsuki, Masao
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Miura, Akihiko; Kato, Junya; Yamashita, Teruo; Shiotsuki, Masao; Matsumoto, Shiro*
no journal, ,
no abstracts in English
Yamashita, Teruo; Masaki, Toshio; Shiotsuki, Masao; Yamasaki, Akito*; Ito, Toshiyuki*; Ono, Isamu*; Matsumoto, Shiro*
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no abstracts in English
Miyauchi, Atsushi; Morikawa, Yo; Sasage, Kenichi; Yamashita, Teruo; Shiotsuki, Masao
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Yamashita, Teruo; Masaki, Toshio; Kojima, Keizo; Shiotsuki, Masao; Ito, Toshiyuki*; Ono, Isamu*; Matsumoto, Shiro*
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Morikawa, Yo; Miyauchi, Atsushi; Nakajima, Masayoshi; Toyoshima, Mikihiro; Yamashita, Teruo; Shiotsuki, Masao; Matsumoto, Shiro*
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Nakazaki, Katsutoshi; Morikawa, Yo; Yamashita, Teruo; Sasage, Kenichi; Nakajima, Masayoshi
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Yamashita, Teruo; Miura, Akihiko; Kato, Junya; Shiotsuki, Masao; Ono, Isamu*; Fukui, Toshiki*; Yamasaki, Akito*; Matsumoto, Shiro*
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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.
Suzuki, Tatsuya*; Kaneshiki, Toshitaka*; Nomura, Masao*; Fujii, Yasuhiko; Kobayashi, Hidekazu; Kano, Shigeru; Yamashita, Teruo
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no abstracts in English
Morikawa, Yo; Miyauchi, Atsushi; Nakajima, Masayoshi; Oyama, Koichi; Yamashita, Teruo; Komamine, Satoshi*; Ochi, Eiji*
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no abstracts in English
Nagai, Takayuki; Oyama, Koichi; Kobayashi, Hidekazu; Morikawa, Yo; Yokozawa, Takuma; Nakajima, Masayoshi; Yamashita, Teruo; Amamoto, Ippei
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no abstracts in English
Yamashita, Teruo; Masaki, Toshio; Nakajima, Masayoshi; Shiotsuki, Masao; Kojima, Keizo; Toyoshima, Mikihiro; Matsumoto, Shiro*
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no abstracts in English