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Journal Articles

General overview of the research project investigating the radionuclide solution behavior in mock mortar matrix modeled after conditions at the Fukushima-Daiichi Nuclear Power Station

Igarashi, Go*; Haga, Kazuko*; Yamada, Kazuo*; Aihara, Haruka; Shibata, Atsuhiro; Koma, Yoshikazu; Maruyama, Ippei*

Journal of Advanced Concrete Technology, 19(9), p.950 - 976, 2021/09

Journal Articles

Oxidative decomposition of ammonium ion with ozone in the presence of cobalt and chloride ions for the treatment of radioactive liquid waste

Aihara, Haruka; Watanabe, So; Shibata, Atsuhiro; Mahardiani, L.*; Otomo, Ryoichi*; Kamiya, Yuichi*

Progress in Nuclear Energy, 139, p.103872_1 - 103872_9, 2021/09

JAEA Reports

Comprehensive treatment of radioactive liquid waste of Chemical Processing Facility

Ogi, Hiromichi*; Arai, Yoichi; Aihara, Haruka; Watanabe, So; Shibata, Atsuhiro; Nomura, Kazunori

JAEA-Technology 2021-007, 27 Pages, 2021/06

JAEA-Technology-2021-007.pdf:2.43MB

Chemical Processing Facility (CPF) of Japan Atomic Energy Agency (JAEA) has been developing the fast reactor fuel reprocessing and vitrification technology. The various kinds of radioactive liquid wastes, which were generated by those experiments and analysis, stored in the hot cells and glove boxes of CPF. The treatment of radioactive liquid wastes were started since July 2015; however, treatment of several kinds of liquid wastes are revealed to be difficult due to contain the various hazardous chemicals. Therefore, in order to establish the new technology suitable for radioactive liquid waste treatment, several collaborative research programs with several universities and national research organizations were started. The combined project lead by JAEA was named to be STRAD (Systematic Treatments of Radioactive liquid wastes for Decommissioning) project. In this project, the process flow for treatment of several actual liquid wastes were established. In this report, treated method and progress of actual liquid wastes of CPF are summarized.

Journal Articles

A Project focusing on the contamination mechanism of concrete after the accident at Fukushima Daiichi Nuclear Power Plant

Yamada, Kazuo*; Maruyama, Ippei*; Haga, Kazuko*; Igarashi, Go*; Aihara, Haruka; Tomita, Sayuri*; Kiran, R.*; Osawa, Norihisa*; Shibata, Atsuhiro; Shibuya, Kazutoshi*; et al.

Proceedings of International Waste Management Symposia 2021 (WM 2021) (CD-ROM), 10 Pages, 2021/03

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

AA2019-0193.pdf:1.29MB

 Times Cited Count:6 Percentile:75.46(Nuclear Science & Technology)

Journal Articles

Stabilization processing of hazardous and radioactive liquid wastes derived from advanced aqueous separation experiments for safety handling and management of waste

Nakahara, Masaumi; Watanabe, So; Ogi, Hiromichi*; Arai, Yoichi; Aihara, Haruka; Motoyama, Risa; Shibata, Atsuhiro; Nomura, Kazunori; Kajinami, Akihiko*

Proceedings of International Nuclear Fuel Cycle Conference / Light Water Reactor Fuel Performance Conference (Global/Top Fuel 2019) (USB Flash Drive), p.66 - 70, 2019/09

A wide variety of hazardous and radioactive liquid waste has generated derived from an advanced aqueous separation experiments in the Chemical Processing Facility. Therefore, they should be stabilized for the safety handling and management. In this study, we report a precipitation or an oxidation for hazardous materials, a solvent extraction for recovery of nuclear materials, and a concentration of solution by a freeze-drying method.

Journal Articles

New project on the analysis of contamination mechanisms of concrete at the Fukushima Daiichi Nuclear Power Station

Yamada, Kazuo*; Maruyama, Ippei*; Koma, Yoshikazu; Haga, Kazuko*; Igarashi, Go*; Shibuya, Kazutoshi*; Aihara, Haruka

Proceedings of International Waste Management Symposia 2019 (WM 2019) (CD-ROM), 6 Pages, 2019/03

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

Minor actinides recovery from irradiated fuel for SmART cycle test

Takeuchi, Masayuki; Sano, Yuichi; Watanabe, So; Nakahara, Masaumi; Aihara, Haruka; Kofuji, Hirohide; Koizumi, Tsutomu; Mizuno, Tomoyasu

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 6 Pages, 2017/04

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:92.19

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

BB2016-0225.pdf:0.61MB

 Times Cited Count:1 Percentile:71.18

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

37 (Records 1-20 displayed on this page)