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Journal Articles

STRAD project for systematic treatments of radioactive liquid wastes generated in nuclear facilities

Watanabe, So; Ogi, Hiromichi*; Arai, Yoichi; Aihara, Haruka; Takahatake, Yoko; Shibata, Atsuhiro; Nomura, Kazunori; Kamiya, Yuichi*; Asanuma, Noriko*; Matsuura, Haruaki*; et al.

Progress in Nuclear Energy, 117, p.103090_1 - 103090_8, 2019/11

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

Journal Articles

Actinides recovery from irradiated fuel for SmART cycle

Sano, Yuichi; Watanabe, So; Nakahara, Masaumi; Aihara, Haruka; Takeuchi, Masayuki

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

JAEA has been promoting MA recycle project using a FR fuel cycle named as SmART cycle concept. The SmART cycle contains the recovery of all actinides, in which total amount of MA is estimated to around 1-2g, at CPF from the FR Joyo spent fuel, the fabrication of MA bearing MOX fuel pellets and pins at AGF with recovered actinides, and the irradiation test of the fabricated fuels at the Joyo. In this paper, recent activities on actinides recovery in CPF, which will make a significant contribution to the SmART cycle, were summarized.

Journal Articles

Research of process to treat the radioactive liquid waste containing chloride ion generated by pyroprocessing plant in operating

Tada, Kohei; Kitawaki, Shinichi; Watanabe, So; Aihara, Haruka; Shibata, Atsuhiro; Nomura, Kazunori

Proceedings of International Nuclear Fuel Cycle Conference (GLOBAL 2017) (USB Flash Drive), 3 Pages, 2017/09

Radioactive liquid waste containing chloride ion (Cl) is generated by chemical analysis for process control of pyroprocessing. To realize discharging this liquid waste to the sea, it's necessary to carry out the process in order to separate Cl and recover U, Pu. This study carried out a combination of the AgCl precipitation method and extraction chromatography method to separate Cl and recover U, Pu. The result of precipitation test showed that U and Pu didn't occur the co-precipitation after the test. The result of solid phase extraction test showed that 95% of Pu was successfully recovered from the liquid waste. It was difficult to analyze $$alpha$$ radioactivity about U because the concentration of U is not enough. These results showed that these process has the feasibility of the discharging the liquid waste to the sea.

Journal Articles

Characterization of the insoluble sludge from the dissolution of irradiated fast breeder reactor fuel

Aihara, Haruka; Arai, Yoichi; Shibata, Atsuhiro; Nomura, Kazunori; Takeuchi, Masayuki

Procedia Chemistry, 21, p.279 - 284, 2016/12

BB2015-3214.pdf:0.31MB

 Times Cited Count:3 Percentile:6.3

Journal Articles

Simulation study of sludge precipitation in spent fuel reprocessing

Takeuchi, Masayuki; Aihara, Haruka; Nakahara, Masaumi; Tanaka, Kotaro*

Procedia Chemistry, 21, p.182 - 189, 2016/12

 Times Cited Count:1 Percentile:26.04

A simulation technology with electrolyte thermodynamic model has been developed to evaluate the precipitation behavior in reprocessing solution based on nitric acid solution. The simulation results were compared with the experiment data from non-radioactive simulated HLLW with ten elements and Pu-Zr-Mo solution, and the reliability of the thermodynamic model was verified. Most of the precipitation species was zirconium molybdate hydrate from the both data. It is demonstrated that the chemical species and amount of the precipitation calculated by thermodynamic model reflected well that of experiments. This study has shown the thermodynamic simulation model is one of the useful tools to estimate the behavior of precipitation from the reprocessing solution.

Journal Articles

Influence of contaminants from spent fuel pools at the Fukushima Daiichi Nuclear Power Station on the reprocessing process

Aihara, Haruka; Kitawaki, Shinichi; Nomura, Kazunori; Taguchi, Katsuya

Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.1076 - 1083, 2015/09

Oral presentation

Improved spectrophotometric method for determination of hydrazine

Aihara, Haruka; Hinai, Hiroshi; Nakajima, Yasuo

no journal, , 

no abstracts in English

Oral presentation

Extraction behavior of dissolved metals from cladding tube by bidentate extractants

Aihara, Haruka; Koma, Yoshikazu; Takeuchi, Masayuki; Koizumi, Tsutomu; Koyama, Shinichi; Takagi, Kazunari*

no journal, , 

no abstracts in English

Oral presentation

Basic study on sludge formation behavior under reprocessing process condition, 2; Characteristic evaluation of sludge from simulated waste composed of 28 elements

Aihara, Haruka; Takeuchi, Masayuki; Koizumi, Tsutomu; Murao, Ayako*; Mimura, Hitoshi*

no journal, , 

no abstracts in English

Oral presentation

Behavior of plutonium on formation of zirconium molybdate hydrate

Nakahara, Masaumi; Aihara, Haruka; Takeuchi, Masayuki; Nakajima, Yasuo; Koizumi, Tsutomu

no journal, , 

To investigate formation properties of zirconium molybdate hydrate in a Pu nitrate solution containing Zr and Mo, formation experiments were carried out in a glove box. The Pu content in zirconium molybdate hydrate obtained by heating for 7 h was slight.

Oral presentation

Influence of impurities from spent fuel pool on solvent extraction process, 1; Behavior of impurities in solvent extraction system

Aihara, Haruka; Hinai, Hiroshi; Kitawaki, Shinichi; Nakajima, Yasuo; Taguchi, Katsuya

no journal, , 

no abstracts in English

Oral presentation

Basic study on sludge formation behavior under reprocessing process condition, 3; Precipitating behavior of tellurium

Aihara, Haruka; Kitawaki, Shinichi; Takeuchi, Masayuki; Syed Masud, R.*; Mimura, Hitoshi*

no journal, , 

no abstracts in English

Oral presentation

Behavior of radioactive materials contained in the accumulated water on Fukushima Daiichi Nuclear Power Station

Aihara, Haruka; Shibata, Atsuhiro; Nomura, Kazunori

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Basic study of separating ammonium ion by using zeolite adsorbent

Miyano, Riku*; Asanuma, Noriko*; Matsuura, Haruaki*; Aihara, Haruka; Watanabe, So; Nomura, Kazunori

no journal, , 

no abstracts in English

Oral presentation

Separation of ammonia from liquid waste containing nuclear material

Miyoshi, Masahide*; Aihara, Haruka; Watanabe, So; Matsuura, Haruaki*

no journal, , 

no abstracts in English

Oral presentation

Ammonium separation and decomposition for radioactive liquid waste treatment, 1; Oxidative decomposition treatment of ammonium with homogeneous catalyst

Aihara, Haruka; Watanabe, So; Nomura, Kazunori; Kamiya, Yuichi*

no journal, , 

no abstracts in English

Oral presentation

Ammonium separation and decomposition for radioactive liquid waste treatment, 2; Separation of ammonium by zeolite absorbent as a pretreatment

Asanuma, Noriko*; Miyano, Riku*; Shimizu, Tomu*; Aihara, Haruka; Watanabe, So; Nomura, Kazunori

no journal, , 

no abstracts in English

Oral presentation

Ammonium separation and decomposition for radioactive liquid waste treatment, 3; Pretreatment process of precipitation and vaporization for ammonium separation

Matsuura, Haruaki*; Kobayashi, Ami*; Miyoshi, Masahide*; Aihara, Haruka; Watanabe, So; Nomura, Kazunori

no journal, , 

no abstracts in English

Oral presentation

29 (Records 1-20 displayed on this page)