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Journal Articles

Decontamination and solidification treatment on spent liquid scintillation cocktail

Watanabe, So; Takahatake, Yoko; Ogi, Hiromichi*; Osugi, Takeshi; Taniguchi, Takumi; Sato, Junya; Arai, Tsuyoshi*; Kajinami, Akihiko*

Journal of Nuclear Materials, 585, p.154610_1 - 154610_6, 2023/11

 Times Cited Count:0 Percentile:0.00(Materials Science, Multidisciplinary)

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.

Oral presentation

Development of low temperature solidification process of radioactive waste liquid by freeze drying method

Kajinami, Akihiko*; Watanabe, So

no journal, , 

no abstracts in English

Oral presentation

Study of low temperature solidification of radioactive waste liquid by freeze drying method

Kajinami, Akihiko*; Watanabe, So

no journal, , 

no abstracts in English

Oral presentation

Development of pyrochemical reprocessing technology based on Co-electrodeposition method, 12; General overview and electrodeposition test

Myochin, Munetaka; Kofuji, Hirohide; Yamana, Hajimu*; Shirai, Osamu*; Yamamura, Tsutomu*; Umesaki, Norimasa*; Matsuura, Haruaki*; Kajinami, Akihiko*; Iwadate, Yasuhiko*; Otori, Norikazu*; et al.

no journal, , 

no abstracts in English

Oral presentation

Immobilization of Tc in radioactive liquid waste using freeze-drying method

Suzuki, Seiya; Watanabe, So; Arai, Yoichi; Nakamura, Masahiro; Kajinami, Akihiko*

no journal, , 

Vitrification technology has been adopted as a treatment technology for high-level radioactive liquid waste (HLLW). In this vitrification process, HLLW is mixed with borosilicate glass that has been heated to over 1000 degree Celsius and melted, and then rapidly cooled to form a chemically stable solidified product. In this way, vitrification technology has already been established. On the other hand, there are some drawbacks of this technology due to the high temperature. Our group is focusing on a procedure to immobilize radioactive species into a chemically stable material at lower temperatures using freeze-drying (FD) technology. In the experiment on simulating HLLW, it was confirmed that major elements such as Ru, Pd and Nd were retained in the solidified material. The retention mechanism of cation groups in the solidified material is presumed to be electrostatic interaction with negatively charged sites in the matrix. However, Mo and Zr were eluted as anionic species. Tc, which is included as an anion species in HLLW, was not targeted in the simulated experiment, but immobilization of volatile Tc is challenging and important. In this study, to establish an immobilization technology of Tc, FD solidification tests on a nitric acid solution of 99Tc were carried out, and the immobilization mechanism of anion species is discussed.

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