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JAEA Reports

Replacement of incinerator adopted to Plutonium Waste Treatment Facility

Yamashita, Kiyoto; Maki, Shota; Yokosuka, Kazuhiro; Fukui, Masahiro; Iemura, Keisuke

JAEA-Technology 2023-023, 97 Pages, 2024/03

JAEA-Technology-2023-023.pdf:8.21MB

The incinerator adopted to incineration room, Plutonium Waste Treatment Facility had been demonstrated since 2002 for developing technologies to reduce the volume of fire-resistant wastes such as vinyl chloride (represented by Polyvinyl chloride bags) and rubber gloves for Radio Isotope among radioactive solid wastes generated by the production of mixed oxide fuels. The incinerator, cooling tower, and processing pipes were replaced with a suspension period from 2018 to 2022, which fireproof materials on the inner wall of the incinerator was cracked and grown caused by hydrogen chloride generated when disposing of fire-resistant wastes. This facility consists of the waste feed process, the incineration process, the waste gas treatment process, and the ash removal process. We replaced the cooling tower in the waste gas treatment process from March 2020 to March 2021, and the incinerator in the incineration process from January 2021 to February 2022. In addition, samples were collected from the incinerator and the cooling tower during the removing and dismantling of the replaced devices, observed by Scanning Electron Microscope and X-ray microanalyzer, and analyzed by X-ray diffraction to investigate the corrosion and deterioration of them. This report describes the method of setting up the green house, the procedure for replacing them, and the results from analysis in corrosion and deterioration of the cooling tower and incinerator.

JAEA Reports

Experiment of incineration for Trans-Uranic (TRU) wastes containing chlorides

Yamashita, Kiyoto; Yokoyama, Aya*; Takagai, Yoshitaka*; Maki, Shota; Yokosuka, Kazuhiro; Fukui, Masahiro; Iemura, Keisuke

JAEA-Technology 2022-020, 106 Pages, 2022/10

JAEA-Technology-2022-020.pdf:4.77MB

Radioactive solid wastes generated by Fukushima Daiichi Nuclear Power Station disaster may contain high levels of salt from the tsunami and seawater deliberately released into the area. It is assumed that polyvinyl chloride (PVC) products may be used for decommissioning work and for containment of radioactive wastes in the future. Among the method of handling them, incineration is one method that needs to be investigated as it is good method for reduction and stabilization of wastes. But in order to dispose of Trans-Uranic (TRU) solid waste containing chlorides, it is necessary to select the structure and materials of the facility based on the information such as the movement of nuclides and chlorides in the waste gas treating system and the corrosion of equipment due to chlorides. Therefore, we decided to get various data necessary to design a study of the incineration facilities. And we decided to examine the transfer behavior of chlorides to the waste gas treatment system, the corrosion-resistance of materials in the incineration facilities, and the distribution survey of plutonium in them obtained using the Plutonium-contaminated Waste Treatment Facility (PWTF), Nuclear Fuel Cycle Engineering Laboratories, which is a unique incinerating facility in Japan. This report describes the transfer behavior of chlorides in the waste gas treatment system, the evaluation of corrosion-resistance materials and the distribution survey of plutonium in the incineration facilities obtained by these tests using the Plutonium-contaminated Waste Treatment Facility, Nuclear Fuel Cycle Engineering Laboratories.

Journal Articles

Incineration technology of plutonium contaminated solid waste generated from MOX fuel fabrication facilities

Shibata, Yuichi

Genshiryoku eye, 57(6), p.60 - 63, 2011/06

Plutonium-contaminated solid wastes have been generated during MOX fuel fabrication in the Japan Atomic Energy Agency (JAEA). Chlorine contained solid wastes such as PVC bags and chloroprene rubber gloves have been steadily generated because MOX fuel fabrication equipments are installed in glove boxes. Incinerations of chlorinated wastes cause the problems such as corrosion of the equipments and dust load against the exhaust system. The JAEA had designed and manufactured a new type incineration system for chlorine contained wastes and combustible wastes based on past experience gained by the operation of the Plutonium contaminated Waste Treatment Facility (PWTF) to solve the problems.

Oral presentation

Demonstrated operation of chlorine contained waste incinerator, 2

Shibata, Yuichi; Tamura, Masanori; Sato, Shunichi; Iimura, Izumi; Usui, Kazuya

no journal, , 

no abstracts in English

Oral presentation

Demonstrated operation of chlorine contained waste incineration system for TRU contaminated wastes

Shibata, Yuichi; Tamura, Masanori; Iimura, Izumi; Usui, Kazuya

no journal, , 

Pu-contaminated solid wastes such as combustible, incombustible and chlorine contained waste have been generated during MOX fuel fabrication in the Japan Atomic Energy Agency (JAEA). Incineration of chlorinated wastes caused the problems such as corrosion of the equipments and dust load against the exhaust system. The JAEA had designed and manufactured a new type incineration system for chlorinated wastes and combustible wastes based on past experience gained by the operation of the Plutonium contaminated Waste Treatment Facility (PWTF) to solve the problems. The incineration system has been operating since June 2002. Plutonium contaminated solid wastes treated so far amount to 216 m$$^{3}$$ (30 ton). The volume reduction ratio was approximately 45 (weight reduction ratio is approximately 12). The incineration system had been operated without contamination in the work environment due to maintain its air-tightness. And significant corrosion wastage could not be observed.

Oral presentation

Operational experience of chlorinated compounds waste incineration system for plutonium contaminated wastes

Shibata, Yuichi; Iimura, Izumi; Usui, Kazuya

no journal, , 

The Japan Atomic Energy Agency (JAEA) has designed and manufactured a new type incineration system for chlorine containing wastes and combustible wastes generated from MOX fuel fabrication facilities. The incineration system has been operating since June 2002. The plant has attained around 6000 hours of operation and treated about 46.4ton (290m$$^{3}$$) of plutonium contaminated solid wastes, as of today. Volatile chloride accumulated at the exhaust gas cooler, resulting in a flow obstruction. The incineration system has successfully and stably operated with periodic cleanup of the accumulated volatile chloride by using remote handling tools.

Oral presentation

Demonstrated operation of chlorine contained waste incinerator, 3

Maki, Shota

no journal, , 

no abstracts in English

Oral presentation

Demonstrated operation of chlorine contained waste incinerator, 4

Maki, Shota; Shibata, Yuichi; Yokosuka, Kazuhiro; Fukui, Masahiro; Iemura, Keisuke; Osawa, Takayasu

no journal, , 

no abstracts in English

Oral presentation

Research for material selection of ash handling equipment of incinerator

Maki, Shota; Fukui, Masahiro; Iemura, Keisuke; Osawa, Takayasu

no journal, , 

no abstracts in English

Oral presentation

Demonstration of an incinerator for flame-retarded TRU wastes, 1; Issues and improvements on the incinerator leading up to treatment of wastes converted into 5000 of 200$$ell$$ waste drums

Maki, Shota; Yokosuka, Kazuhiro; Fukui, Masahiro; Iemura, Keisuke; Osawa, Takayasu

no journal, , 

no abstracts in English

Oral presentation

Demonstration of an incinerator for flame-retarded TRU wastes, 2; Replacement of instruments adopted by the incinerator for future use

Yokosuka, Kazuhiro; Maki, Shota; Fukui, Masahiro; Shibata, Yuichi; Iemura, Keisuke; Osawa, Takayasu

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Development of incineration technology for plutonium contaminated flame retardant waste containing chloride compound

Maki, Shota; Yokosuka, Kazuhiro; Fukui, Masahiro; Iemura, Keisuke; Osawa, Takayasu

no journal, , 

no abstracts in English

Oral presentation

Improvement on maintenance and operative performance for plutonium contaminated flame retardant wastes containing chloride compound

Fukui, Masahiro; Yokosuka, Kazuhiro; Maki, Shota; Shibata, Yuichi; Shigihara, Yuta; Ouchi, Takahiro; Minouchi, Hiroyuki; Iemura, Keisuke

no journal, , 

no abstracts in English

Oral presentation

A Replacement plan of major refractory parts of an existing incinerator for plutonium contaminated wastes to extend its lifetime

Maki, Shota; Yokosuka, Kazuhiro; Shibata, Yuichi; Fukui, Masahiro; Iemura, Keisuke

no journal, , 

no abstracts in English

Oral presentation

A Replacement plan of major refractory parts of an existing incinerator for plutonium contaminated wastes to extend its lifetime

Sawada, Sho; Maki, Shota; Yokosuka, Kazuhiro; Fukui, Masahiro; Iemura, Keisuke; Osawa, Takayasu

no journal, , 

no abstracts in English

Oral presentation

Development test for the mineralization device of analytical waste liquid

Hirota, Kenji; Kikuchi, Takahiro; Konno, Takahiro; Sekine, Naoki; Tazawa, Yuto

no journal, , 

no abstracts in English

Oral presentation

Demonstration of an incinerator for flame-retarded TRU wastes, 8; Replacing of the cooling tower

Yamashita, Kiyoto; Maki, Shota; Yokosuka, Kazuhiro; Fukui, Masahiro; Iemura, Keisuke

no journal, , 

no abstracts in English

Oral presentation

Exam for the Mineralization of Analytical waste liquid; Metal ion, processing speed comparing

Kikuchi, Takahiro; Hirota, Kenji; Konno, Takahiro; Sekine, Naoki; Tazawa, Yuto

no journal, , 

Since the Karl Fischer method generates waste liquid containing organic solvents, its disposal method is an issue in nuclear facilities. A solution containing an organic solvent was put into a nitric acid solution containing metal ions, and then decomposed by an electrochemical method and ultrasonic waves to mineralize it. In this presentation, the correlation between the type of metal ions and processing speed, and the correlation between the amount of solution containing organic solvent and processing speed will be reported.

Oral presentation

Demonstration of an incinerator for flame-retarded TRU wastes, 9; Technical report on renewal of incinerator for incinerating waste containing alpha nuclides

Maki, Shota; Yamashita, Kiyoto; Yokosuka, Kazuhiro; Fukui, Masahiro; Watahiki, Masatoshi

no journal, , 

Plutonium contaminated flame retardant wastes often contain chlorides it has become a key issue to establish required technologies for incinerating them, effectively. However, due to long-term operation, multiple cracks originating from the combustion air holes that supply combustion-promoting air into the furnace and the refractory inside the incinerator become more embrittled, making it difficult to continue safe operation. As a result, we set up an enclosure to prevent the spread of contamination, replaced the incinerator within it, and obtained data that can be reflected in the development of future incineration equipment.

Oral presentation

Exam for the mineralization of analytical waste liquid; Comparison of cathode materials

Konno, Takahiro; Kikuchi, Takahiro; Sekine, Naoki; Tazawa, Yuto

no journal, , 

Plutonium Fuel Development Center, Japan Atomic Energy Agency plans to change the moisture analysis to the Karl Fischer method. This method generates waste liquid containing organic solvents. In Plutonium Fuel Development Center, since a treatment method for radioactive waste liquid containing organic solvents has not been established, we are developing a technology to mineralize organic solvents by electrochemical-method as a candidate. In this presentation, comparison results of cathode materials to be used for electrochemical-method will be reported.

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