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Journal Articles

Zr separation from high-level liquid waste with a novel hydroxyacetoamide type extractant

Morita, Keisuke; Suzuki, Hideya; Matsumura, Tatsuro; Takahashi, Yuya*; Omori, Takashi*; Kaneko, Masaaki*; Asano, Kazuhito*

Proceedings of International Nuclear Fuel Cycle Conference / Light Water Reactor Fuel Performance Conference (Global/Top Fuel 2019) (USB Flash Drive), p.464 - 468, 2019/09

High level liquid waste (HLLW) contains several radionuclides with half-lives longer than 10$$^{6}$$ year. For reduce environmental burden of waste disposal, minor actinoids and long-lived fission products will to be partitioned and transmuted. JAEA and Toshiba developed process for recovering Se, Zr, Pd and Cs from HLLW. Solvent extraction for Zr with novel extractant, ${it N,N}$-didodecyl-2-hydroxyacetoamide (HAA) was detailed. The HAA system showed high selectivity for Zr, as indicated by the extraction order of Zr $$>$$ Mo $$>$$ Pd $$>$$ Ag $$approx$$ Sb $$>$$ Sn $$>$$ Lns $$>$$ Fe. The extracted species was determined as Zr(HAA)$$_{3}$$(NO$$_{3}$$)$$_{4}$$(HNO$$_{3}$$)$$_{x}$$. A continuous countercurrent extraction with HAA was applied to a simulated, concentrated HLLW after Pd, Se, and Cs removal, where the quantitative extraction of Zr and Mo was effectively demonstrated.

Journal Articles

Reduction and resource recycling of high-level radioactive wastes through nuclear transmutation; Isolation techniques of Pd, Zr, Se and Cs in simulated high level radioactive waste using solvent extraction

Sasaki, Yuji; Morita, Keisuke; Ito, Keisuke; Suzuki, Shinichi; Shiwaku, Hideaki; Takahashi, Yuya*; Kaneko, Masaaki*; Omori, Takashi*; Asano, Kazuhito*

Proceedings of International Nuclear Fuel Cycle Conference (GLOBAL 2017) (USB Flash Drive), 4 Pages, 2017/09

no abstracts in English

Journal Articles

Analysis on ex-vessel loss of coolant accident for a water-cooled fusion DEMO reactor

Watanabe, Kazuhito; Nakamura, Makoto; Tobita, Kenji; Someya, Yoji; Tanigawa, Hisashi; Uto, Hiroyasu; Sakamoto, Yoshiteru; Araki, Takao*; Asano, Shiro*; Asano, Kazuhito*

Proceedings of 26th IEEE Symposium on Fusion Engineering (SOFE 2015), 6 Pages, 2016/06

Safety studies of a water-cooled fusion DEMO reactor have been performed. In the event of the blanket cooling pipe break outside the vacuum vessel, i.e. ex-vacuum vessel loss of coolant accident (ex-VV LOCA), the pressurized steam and air may lead to damage reactor building walls which have confinement function, and to release the radioactive materials to the environment. In response to this accident, we proposed three cases of confinement strategies. In each case, the pressure and thermal loads to the confinement boundaries and total mass of tritium released to outside the boundaries were analyzed by accident analysis code MELCOR modified for fusion reactor. These analyses developed design parameters to maintain the integrity of the confinement boundaries.

Oral presentation

Solvent extraction and separation of Se, Zr, Pd, and Cs having long lived radionuclides, 2; Systematic separation of Se, Zr, Pd, and Cs using different extractants

Sasaki, Yuji; Suzuki, Shinichi; Shiwaku, Hideaki; Ito, Keisuke; Takahashi, Yuya*; Kaneko, Masaaki*; Omori, Takashi*; Asano, Kazuhito*

no journal, , 

no abstracts in English

Oral presentation

Reduction and resource recycling of high-level radioactive wastes through nuclear transmutation; From viewpoint of reprocessing and recycling, 1; Separation and recovery of LLFP from high-level liquid wastes

Sasaki, Yuji; Morita, Keisuke; Suzuki, Shinichi; Shiwaku, Hideaki; Ito, Keisuke; Takahashi, Yuya*; Kaneko, Masaaki*; Asano, Kazuhito*

no journal, , 

no abstracts in English

Oral presentation

Recovery of LLFP from high-level liquid waste, 3; Properties of solvent for the replacement of n-dodecane

Sasaki, Yuji; Suzuki, Shinichi; Kobayashi, Toru; Ito, Keisuke*; Takahashi, Yuya*; Kaneko, Masaaki*; Asano, Kazuhito*

no journal, , 

At ImPACT project, we investigate more safety and effect disposal method by using separation of long-lived radioactive nuclides and their transmutation from high-level radioactive waste (HLW). High concentration of Zr in simulated HLW is extracted by HDEHP or TODGA, so we study on properties of diluents instead of n-dodecane. Especially we study on the radiolysis. After irradiation of TODGA dissolved in different 5 diluents, we use these extraction solvents as solvent extraction of Nd. It is found that distribution ratio of Nd decrease with irradiation time.

Oral presentation

Recovery of LLFP from high-level liquid waste, 4; Investigation of new extractants for recovery of Zirconium

Morita, Keisuke; Suzuki, Hideya; Matsumura, Tatsuro; Takahashi, Yuya*; Omori, Takashi*; Kaneko, Masaaki*; Asano, Kazuhito*

no journal, , 

no abstracts in English

Oral presentation

Separation process of long-lived fission products from high-level radioactive wastes; Separation and recovery technologies based on electrolysis, adsorption, and solvent extraction

Takahashi, Yuya*; Omori, Takashi*; Yamashita, Yu*; Kaneko, Masaaki*; Asano, Kazuhito*; Morita, Keisuke; Suzuki, Hideya*; Matsumura, Tatsuro

no journal, , 

no abstracts in English

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