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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

Dioxin decomposition/elimination technology using electron beams

Kojima, Takuji; Hirota, Koichi; Taguchi, Mitsumasa; Hakoda, Teruyuki; Takigami, Machiko

Proceedings of 25th JAIF-KAIF Seminar on Nuclear Industry, p.193 - 201, 2003/00

The electron beam technology for decomposition/elimination of dioxin contained in flue gas has been developed using real waste gas of 1,000 m$$^{3}$$N/h released from the municipal solid waste incineration facility at 200$$^{circ}$$C. The decomposition efficiency, the ratio of toxic equivalent dioxin concentration before and after EB irradiation to doses above 15kGy is higher than 90%, which clears the regulation limit in the Japanese special measures of dioxin release. The chemical process of dioxin decomposition was studied and low-toxicity of irradiated gas was confirmed in terms of endocrine disrupter influence.

Journal Articles

Electron-beam treatment of PCDD/Fs in the flue gas from a municipal solid waste incinerator

Hirota, Koichi; Hakoda, Teruyuki; Taguchi, Mitsumasa; Takigami, Machiko*; Kojima, Takuji

Proceedings of 9th International Conference on Radiation Curing (RadTech Asia '03) (CD-ROM), 4 Pages, 2003/00

The flue gas from a municipal solid waste incinerator (MSWI) was irradiated with electron beams to destroy polychlorinated dibenzo-p-dioxins (PCDDs) and polychlorinated dibenzofurans (PCDFs). A flue gas of 1,000 m$$^{3}$$/h N for the irradiation was obtained at 200$$^{circ}$$C from a main gas stream of the MSWI. The decomposition efficiencies of PCDD/Fs were increased with absorbed dose and reached 90% at a dose of 14 kGy. The reaction mechanisim for PCDD/Fs was also considered.

JAEA Reports

Reactor physics activities in Japan; July, 1992 $$sim$$ July, 1993

Research Committee on Reactor Physics

JAERI-M 93-254, 36 Pages, 1994/01

JAERI-M-93-254.pdf:1.27MB

no abstracts in English

Journal Articles

Application of an advanced incineration technique to spent solvent treatment for improving the waste management

Uchiyama, Gunzo; Maeda, Mitsuru; *; Fujine, Sachio; *; *

Proceedings of 4th International Conference on Nuclear Fuel Reprocessing and Waste Management; RECOD '94, Vol.3, 0, p.1 - 15, 1994/00

no abstracts in English

JAEA Reports

Reactor physics activities in Japan; June 1991 $$sim$$ July 1992

Research Committee on Reactor Physics

JAERI-M 92-209, 43 Pages, 1993/01

JAERI-M-92-209.pdf:1.43MB

no abstracts in English

Journal Articles

The Incineration treatment of combustible solid waste at Tokai, JAERI

; ;

NGK Genshiryoku Giho, 0(3), p.4 - 13, 1991/03

no abstracts in English

JAEA Reports

Core design study for hybrid type trans-uranium nuclides incineration plant, Part 1; Concept

Takada, Hiroshi; Kanno, Ikuo; Takizuka, Takakazu; Akabori, Mitsuo; ; Kaneko, Yoshihiko

JAERI-M 90-131, 18 Pages, 1990/08

JAERI-M-90-131.pdf:0.59MB

no abstracts in English

JAEA Reports

Volume reduction of ion exchange resins by catalytic incineration, III; Investigation of overall reaction rate

Yahata, Taneaki; *; Hirata, Masaru

JAERI-M 90-075, 68 Pages, 1990/05

JAERI-M-90-075.pdf:1.7MB

no abstracts in English

Journal Articles

Incineration method for plutonium recovery from alpha-contaminated organic compounds

Inorg.Chim.Acta, 140, p.279 - 282, 1987/00

no abstracts in English

Journal Articles

Behavior of tritium water in radioactive waste incineration plant

;

Radioisotopes, 29(10), p.484 - 489, 1980/00

no abstracts in English

13 (Records 1-13 displayed on this page)
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