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JAEA Reports

Stabilization treatment of nuclear fuel material contained with organic matter

Senzaki, Tatsuya; Arai, Yoichi; Yano, Kimihiko; Sato, Daisuke; Tada, Kohei; Ogi, Hiromichi*; Kawanobe, Takayuki*; Ono, Shimpei; Nakamura, Masahiro; Kitawaki, Shinichi; et al.

JAEA-Testing 2022-001, 28 Pages, 2022/05

JAEA-Testing-2022-001.pdf:2.33MB

In preparation for the decommissioning of Laboratory B of the Nuclear Fuel Cycle Engineering Laboratory, the nuclear fuel material that had been stored in the glove box for a long time was moved to the Chemical Processing Facility (CPF). This nuclear fuel material was stored with sealed by a polyvinyl chloride (PVC) bag in the storage. Since it was confirmed that the PVC bag swelled during storage, it seems that any gas was generated by radiolysis of the some components contained in the nuclear fuel material. In order to avoid breakage of the PVC bag and keep it safety for long time, we began the study on the stabilization treatment of the nuclear fuel material. First, in order to clarify the properties of nuclear fuel material, radioactivity analysis, component analysis, and thermal analysis were carried out. From the results of thermal analysis, the existence of organic matter was clarified. Then, ion exchange resin with similar thermal characteristics was selected and the thermal decomposition conditions were investigated. From the results of these analyzes and examinations, the conditions for thermal decomposition of the nuclear fuel material contained with organic matter was established. Performing a heat treatment of a small amount of nuclear fuel material in order to confirm the safety, after which the treatment amount was scaled up. It was confirmed by the weight change after the heat treatment that the nuclear fuel material contained with organic matter was completely decomposed.

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

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

Waste management in a Hot Laboratory of Japan Atomic Energy Agency, 3; Volume reduction and stabilization of solid waste

Nakahara, Masaumi; Watanabe, So; Ogi, Hiromichi*; Shibata, Atsuhiro; Nomura, Kazunori

International Journal of Nuclear and Quantum Engineering (Internet), 13(4), p.191 - 194, 2019/04

High level radioactive solid waste is reduced the volume or stabilized in the Chemical Processing Facility in the Japan Atomic Energy Agency. A plastic product is molten with a heating mantle and reduced the volume. A non-flammable such as metal is cut with a band saw machine for reducing the volume. A used adsorbent in the extraction chromatograph process was heated with an electric furnace using non-radioactive materials, and the experimental result suggests that organic materials in the used adsorbent were decomposed stably.

Journal Articles

Waste management in a Hot Laboratory of Japan Atomic Energy Agency, 2; Condensation and solidification experiments on liquid waste

Watanabe, So; Ogi, Hiromichi*; Shibata, Atsuhiro; Nomura, Kazunori

International Journal of Nuclear and Quantum Engineering (Internet), 13(4), p.169 - 174, 2019/04

As a part of STRAD project conducted by JAEA, condensation of radioactive liquid waste containing various chemical compounds using reverse osmosis (RO) membrane filter was examined for efficient and safety treatment of the liquid wastes accumulated inside hot laboratories. NH$$_{4}$$$$^{+}$$ ion in the feed solution was successfully concentrated, and NH$$_{4}$$$$^{+}$$ ion involved in the effluents became lower than target value; 100 ppm. Solidification of simulated aqueous and organic liquid wastes was also tested. Those liquids were successfully solidified by adding cement or coagulants. Nevertheless, optimization in materials for confinement of chemicals is required for long time storage of the final solidified wastes.

Journal Articles

Waste management in a hot laboratory of Japan Atomic Energy Agency, 1; Overview and activities in chemical processing facility

Nomura, Kazunori; Ogi, Hiromichi*; Nakahara, Masaumi; Watanabe, So; Shibata, Atsuhiro

International Journal of Nuclear and Quantum Engineering (Internet), 13(5), p.209 - 212, 2019/00

Journal Articles

Effect of non-uniform heat transfer coefficient on melting of phase change materials in horizontal circular cylinders

Ogi, Hiromichi*; Shiina, Yasuaki; Inagaki, Terumi*

Nihon Kikai Gakkai Rombunshu, B, 74(748), p.2588 - 2597, 2008/12

no abstracts in English

Journal Articles

Melting characteristics of solid phase in horizontal cylindrical enclosures with non-uniform surface heat transfer coefficient

Shiina, Yasuaki; Ogi, Hiromichi*; Inagaki, Terumi*

Nihon Kikai Gakkai Netsu Kogaku Konfarensu 2007 Koen Rombunshu, p.245 - 246, 2007/11

no abstracts in English

Journal Articles

Close contact melting of solid in a horizontal cylindrical capsule

Nemoto, Hiroyuki*; Ogi, Hiromichi*; Shiina, Yasuaki; Inagaki, Terumi*

Kashika Joho Gakkai-Shi, 26(Suppl.1), p.1 - 4, 2006/07

no abstracts in English

Journal Articles

Contact melting heat transfer in horizontal cylindrical enclosures by surrounded uniform flows

Shiina, Yasuaki; Nemoto, Hiroyuki*; Ogi, Hiromichi*; Inagaki, Terumi*

Dai-43-Kai Nihon Dennetsu Shimpojiumu Koen Rombunshu, p.415 - 416, 2006/05

no abstracts in English

Journal Articles

Effect of non-uniform heat transfer coefficient on melting characteristics of cylindrical heat storage capsules

Ogi, Hiromichi*; Shiina, Yasuaki; Inagaki, Terumi*

Dai-43-Kai Nihon Dennetsu Shimpojiumu Koen Rombunshu, p.413 - 414, 2006/05

no abstracts in English

Journal Articles

Analysis on contact melting of phase change materials in cylindrical capsules

Shiina, Yasuaki; Ogi, Hiromichi*; Inagaki, Terumi*

Nihon Kikai Gakkai Tohoku Shibu Dai-41-Ki Sokai, Koenkai Koen Rombunshu, p.83 - 84, 2006/03

no abstracts in English

Oral presentation

Melting heat transfer of solid phase in horizontal cylindrical enclosures

Nemoto, Hiroyuki*; Shiina, Yasuaki; Inagaki, Terumi*; Ogi, Hiromichi*

no journal, , 

no abstracts in English

Oral presentation

Oxidative decomposition of lactic acid in radioactive liquid waste

Arai, Yoichi; Watanabe, So; Ogi, Hiromichi*; Kubota, Toshio*; Nomura, Kazunori

no journal, , 

no abstracts in English

Oral presentation

Treatments of radioactive waste solutions generated in a hot laboratory of Japan Atomic Energy Agency

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

no journal, , 

Oral presentation

STRAD project for treatment of radioactive liquid waste; Overview of the project

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

no journal, , 

no abstracts in English

Oral presentation

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

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

no journal, , 

Oral presentation

Treatment of spent solvent in STRAD project

Watanabe, So; Arai, Yoichi; Ogi, Hiromichi*; Nakamura, Masahiro; Shibata, Atsuhiro; Osugi, Takeshi; Taniguchi, Takumi; Sone, Tomoyuki; Nomura, Kazunori

no journal, , 

Oral presentation

Efforts on treatment of radioactive liquid waste at Chemical Processing Facility; Development on treatment method for chloride ion containing radioactive liquid waste

Tada, Kohei; Arai, Yoichi; Watanabe, So; Ogi, Hiromichi*; Nakamura, Masahiro; Shibata, Atsuhiro

no journal, , 

no abstracts in English

Oral presentation

Current status of STRAD project for liquid waste management

Watanabe, So; Aihara, Haruka; Takahatake, Yoko; Arai, Yoichi; Ogi, Hiromichi*; Nakamura, Masahiro; Shibata, Atsuhiro; Nomura, Kazunori

no journal, , 

21 (Records 1-20 displayed on this page)