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Oral presentation

Oral presentation

MOX reprocessing at TRP, 1; Overview of recent operational experience (1)

Suda, Shizuka; Taguchi, Katsuya; Iwabuchi, Hiroki

no journal, , 

no abstracts in English

Oral presentation

Investigation concerning radiation deterioration of panel made of plastic, 2

Kawakami, Akihiro; Suda, Shizuka; Shichi, Ryo; Iwabuchi, Hiroki

no journal, , 

The investigation concerning the radiation deterioration of the panel made of plastic set up for the expansion prevention of pollution (Part 2) was done in the maintenance area in the Tokai reprocessing plant shearing processing facilities.

Oral presentation

MOX reprocessing at TRP, 2; Characteristics of MOX shearing

Kuroda, Yasuji; Shichi, Ryo; Iwabuchi, Hiroki

no journal, , 

In the Tokai reprocess facilities machine processing line, the shearing characteristic examination that used advanced converter "FUGEN" MOX type B used fuel was executed. In this report, it reports on properties of the shearing energy evaluated by this examination and the fragment and the shearing powder not done.

Oral presentation

Establishment of estimation approach of shearing force at TRP, 1; Study of estimation approach of shearing force

Suda, Shizuka; Shichi, Ryo; Iwabuchi, Hiroki

no journal, , 

no abstracts in English

Oral presentation

Establishment of estimation approach of shearing force at TRP, 2; Verification of estimation approach of shearing force

Kuroda, Yasuji; Shichi, Ryo; Iwabuchi, Hiroki

no journal, , 

The structural fuel judged to be able to shear by the shearing force presumption technique without the shearing experience so far was actually shorn in the TRP, and the verification of the shearing force presumption technique was verified.

Oral presentation

Step of the improvement of incell- crane for mechanical process in Tokai Reprocessing Plant

Nanko, Masayuki; Ito, Shinichi; Shichi, Ryo; Iwabuchi, Hiroki

no journal, , 

Four cranes are installed in a cell in the shear processing process of the TRP. I experience various kinds of malfunction at first and, in the crane in these cells, report setting about step of the improvement that I performed to overcome them.

Oral presentation

Remote decontamination technology of hot cell in the shearing process at TRP

Nanko, Masayuki; Kawakami, Akihiro; Ito, Shinichi; Shichi, Ryo; Iwabuchi, Hiroki

no journal, , 

no abstracts in English

Oral presentation

Maintenance results of fuel receipt and storage process at TRP

Takeyasu, Shinji; Shichi, Ryo; Iwabuchi, Hiroki

no journal, , 

no abstracts in English

Oral presentation

MOX reprocessing at TRP, 9; Development of hull monitor for MOX spent fuel, 2; Comparison and evaluation of destructive analysis and nondestructive assay

Suda, Shizuka; Tanaka, Makoto; Kuno, Takehiko; Shichi, Ryo; Iwabuchi, Hiroki

no journal, , 

no abstracts in English

Oral presentation

Development of noble metals-compatible vitrification melter in Tokai Vitrification Facility

Kobayashi, Hidekazu; Kodaka, Akira; Iwabuchi, Hiroki

no journal, , 

In JAEA's Tokai Vitrification Facility (TVF) at Tokai Reprocessing Plant (TRP) site, high level liquid waste (HLLW) generated from reprocessing of spent fuels is vitrified with a liquid-fed joule-heated ceramic melter (LFCM). As noble metals (NMs) in HLLW aren't soluble to the glass, and have low resistivity and higher density, they deposit on bottom of melter and form electrical path and thus disturb melter operation. The first and second TVF melter have square pyramidal shaped bottom and issue that NMs on the bottom are difficult to drain out and have to be removed periodically. To solve this issue, we are developing the third melter with conical shaped bottom. The effect of changing the bottom structure was confirmed by thermo-fluid analysis code. Structural optimization of strainer in the upper part of drain nozzle was carried out by visualization experiment. In this meeting, activity of third melter development including past melter structure will be introduced.

Oral presentation

The Risk reduction in Tokai Reprocessing Plant by vitrification of high level liquid waste (HLLW)

Ayame, Yasuo; Iwabuchi, Hiroki; Omori, Eiichi; Miura, Nobuyuki

no journal, , 

Tokai Reprocessing Plant (TRP) is preparing for decommissioning and dismantling, and it takes decades for completion. As about 360 m$$^{3}$$ of HLLW in TRP has risk of evaporation and hydrogen explosion, it must be controlled safely by keeping forced cooling and hydrogen exhausting. So, it was decided to vitrify in Tokai Vitrification Facility (TVF) by 2028 to reduce the risk. TVF was constructed in 1992 and vitrified 306 canisters until now. Full remote maintenance system is adopted for vitrification melter and HLLW tank in the cell. As noble metals in HLLW accumulate at bottom of melter, the melter must be emptied periodically and the noble metals must be removed with mechanical device. For the success of the vitrification, it is necessary to maintain the equipment by organized maintenance plan considering its aging, to expand the capacity to store canisters and to replace the melter within its design life. In this meeting, vitrification plan at Tokai site will be introduced.

Oral presentation

The Outline of "Basic Research Programs of Vitrification Technology for Waste Volume Reduction"

Ishio, Takahiro*; Kanehira, Norio*; Hoshino, Takeshi*; Fukui, Toshiki*; Iwabuchi, Hiroki; Tsukada, Takeshi*

no journal, , 

In Japan, the High Level radioactive Liquid Waste (HLLW) generated along with the nuclear fuel cycle is to be vitrified, and its vitrification technology has been made practicable. And, various kinds of Low Level radioactive Liquid Waste (LLW) generated from reprocessing plant and nuclear power plants in Japan have been primarily treated by various methods such as incineration, compaction, cement solidification, however, vitrification method have not been introduced. On the other hand, there is a potential generation of LLW which has relatively high radioactivity level in case of conducting the decommissioning of reprocessing plant and nuclear power plants. Therefore, various kinds of the solidification and the volume reduction technologies have been developed in order to ensure the stable forms with smaller volumes for the LLW disposal. Furthermore, if the foundation for LLW vitrification technology is developed, it can be reflected in the advancement of vitrification technology of HLLW. Therefore, the Ministry of Economy, Trade and Industry launched the project "Basic Research Programs of Vitrification Technology for Waste Volume Reduction" during FY 2014 - 2018. IHI Corporation (IHI), Japan Nuclear Fuel Limited (JNFL), Japan Atomic Energy Agency (JAEA) and Central Research Institute of Electric Power Industry (CRIEPI) have commissioned this project. The development goals for this project are as follows. (1) To develop LLW generated at nuclear power plants and reprocessing plant, etc., to reinforce the foundation of vitrification technology for high volume reduction and more stable waste. (2) To study also advanced improvement of vitrification of HLLW that is practically used in Japan, by reflecting the findings obtained from LLW infrastructures. In this presentation we will report on our past achievements and future plans in this project.

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