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Journal Articles

Research and development on simplified pelletizing fuel fabrication system

Kawaguchi, Koichi

Dai-4-Kai Saishori Risaikuru Semina Tekisuto, P. 147, 2006/05

no abstracts in English

Journal Articles

Research and development for advanced aqueous reprocessing system in JAEA

Nakabayashi, Hiroki; Koma, Yoshikazu; Nakamura, Hirofumi; Sato, Koji

Dai-4-Kai Saishori Risaikuru Semina Tekisuto, p.142 - 146, 2006/05

no abstracts in English

Oral presentation

Determination of neptunium in Tokai reprocessing plant; Determination of neptunium by $$gamma$$ spectrometry in nitric acid media

Kitao, Takahiko; Nemoto, Hirokazu*; Yamada, Keiji; Sakai, Toshio

no journal, , 

no abstracts in English

Oral presentation

Development of the simplified MOX fuel fabrication process, Short Process; Plutonium test of improving fludity of the powder

Mukai, Yasunobu; Kato, Yoshiyuki; Kimura, Yuichi*; Nemoto, Ryo*

no journal, , 

no abstracts in English

Oral presentation

Computational chemistry for evaluation of actinide extraction system

Hirata, Masaru; Kimura, Takaumi; Yoshizuka, Kazuharu*

no journal, , 

no abstracts in English

Oral presentation

Separation of MA by extraction chromatography

Hoshi, Harutaka*; Wei, Y.*; Kumagai, Mikio*; Asakura, Toshihide; Morita, Yasuji

no journal, , 

no abstracts in English

Oral presentation

Study on extraction separation process by monoamide

Ban, Yasutoshi; Asakura, Toshihide; Morita, Yasuji

no journal, , 

Monoamide compounds are porposed as complete incinereable extractants for aqueous reprocessing of nuclear spent fuel. The performance of the reprocessing processes where N,N-di-(2-ethyl)hexyl-butanamide is used as extractant is evaluated based on concentration profiles of U and Pu calculated with the consideration of acid and element concentration effects on the distribution ratios of U and Pu.

Oral presentation

Development of a long-life vitrification melter

Kato, Junya; Miyauchi, Atsushi; Aoshima, Atsushi; Shiotsuki, Masao; Yamashita, Teruo; Nakajima, Masayoshi; Morikawa, Yo; Miura, Akihiko; Fukui, Toshiki*; Yamasaki, Akito*; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of a simple reprocessing process by selective precipitation for uranyl ions

Kikuchi, Toshiaki*; Yamasaki, Kazuhiko*; Kusama, Makoto*; Chikazawa, Takahiro*; Tamaki, Yoshihisa*; Hanzawa, Masatoshi*; Koshino, Nobuyoshi*; Asanuma, Noriko*; Harada, Masayuki*; Kawata, Yoshihisa*; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of N,N-dialkylamides for reprocessing spent FBR fuel

Suzuki, Shinichi; Yaita, Tsuyoshi; Kimura, Takaumi

no journal, , 

no abstracts in English

Oral presentation

Fundamental research on partitioning-transmutation technology; Literature survey on Sr adsorption by inorganic adsorbents

Asakura, Toshihide; Morita, Yasuji

no journal, , 

Separation of heat-producing fission products, i.e. Cs and Sr, will contribute to reasonable disposal of high level waste, because the wastes produces less heat. The separated Cs or Sr can be utilized as radiation source (Cs) or heat source (Sr). In the research on partitioning process, separation technology of Cs and Sr with inorganic adsorbents (zeolite, titanic acid) was developed. To enhance the applicability of this technology, it is important to develop a new adsorbent, which can separate Cs and Sr from highly acidic solution, i.e. several mol/L of nitric acid. Here, the results of literature survey on adsorbents of Sr are reported. Most of the literatures, which reported adsorptive distribution coefficients of Sr in nitric acid with HNO$$_{3}$$ concentration of 1 mol/L or more, were about antimonic acid compounds. The highest adsorptive distribution coefficient was reported in the literature of pure antimonic acid.. If a compound is consisted of Sb and an additional metal element, the reported adsorptive distribution coefficient of the compound seems to decrease. The selectivity of Sr against Eu seems to increase, if the nitric acid concentration increases.

Oral presentation

Outline of feasibility study on commercialized fast reactor cycle systems in Japan

Tanaka, Toshihiko; Sato, Koji

no journal, , 

The objectives, studied concepts, the selection of the promising concepts and the load to a commercialized operation, as a result of the feasibility study Phase-2 on commercialized fast reactor cycle systems in Japan, will be explained.

Oral presentation

Advanced loop type sodium-cooled fast reactor

Aizawa, Kosuke; Ando, Masato; Kotake, Shoji; Hayashi, Hideyuki; Hayafune, Hiroki; Fujii, Tadashi; Sato, Ikken; Kaito, Takeji

no journal, , 

no abstracts in English

Oral presentation

Development of innovative microchip equipment for analyzing solutions in PUREX reprocessing processes

Hotokezaka, Hiroyasu*; Ban, Yasutoshi; Ikeda, Hidematsu*; Harada, Masayuki*; Mizuguchi, Koji*; Saso, Michitaka*; Sugai, Hiroshi*; Tokeshi, Manabu*; Ikeda, Yasuhisa*; Morita, Yasuji; et al.

no journal, , 

The following items were studied for developing innovative equipment for analysis that provides high-sensitivity and rapid analysis for ultra small amount of samples utilizing microchip and thermal lens detector: Optimum flow condition for forming two-phase steady laminar flow in micro channel, applicability of thermal lens detector for U(VI) and H$$^{+}$$ concentration analysis, extraction properties of U(VI) from aqueous phase to organic phase in micro channel, and radiation resistance of microchips and capillary tubes. In this presentation the summary of these items are reported.

Oral presentation

Flexible fuel cycle initiative

Yamashita, Junichi*; Fukasawa, Tetsuo*; Kawamura, Fumio*; Hoshino, Kuniyoshi*; Sasahira, Akira*; Sato, Seichi*; Minato, Kazuo

no journal, , 

no abstracts in English

Oral presentation

Pyrochemical process of spent oxide fuels by molten fluoride/liquid metal extraction

Sato, Nobuaki*; Takenaka, Toshihide*; Hayashi, Hirokazu; Amano, Osamu*; Kawamura, Fumio*

no journal, , 

no abstracts in English

Oral presentation

17 (Records 1-17 displayed on this page)
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