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Journal Articles

Project management efforts in the decommissioning project of Tokai Reprocessing Plant

Taguchi, Shigeo; Taguchi, Katsuya; Makino, Risa; Yamanaka, Atsushi; Suzuki, Kazuyuki; Takano, Masato; Koshino, Katsuhiko; Ishida, Michihiko; Nakano, Takafumi; Yamaguchi, Toshiya

Nihon Hozen Gakkai Dai-17-Kai Gakujutsu Koenkai Yoshishu, p.499 - 502, 2021/07

In 2018, Tokai Reprocessing Plan (TRP) shifted to the decommissioning stage. In order to proceed with steady decommissioning work, TRP effort to enhance project management function. This paper describes the establishment and role of the Decommissioning Project Management Office, effectiveness of applying the project management tool and its utilization concept, and the method of materialize the equipment dismantling plan.

Journal Articles

Characterization of the dissolver sludge of MOX spent fuel at the Tokai Reprocessing Plant

Suzuki, Kazuyuki; Hatanaka, Akira; Samoto, Hirotaka; Suwa, Toshio; Tanaka, Kosuke; Tanaka, Yukiyoshi

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 6 Pages, 2011/12

The properties of the sludge in dissolver vessels from the reprocessing of ATR-MOX and ATR-UO$$_{2}$$ fuels were investigated on the pilot-plant scale at the Tokai Reprocessing Plant (TRP). This sludge is mainly composed of platinum-group elements, zircaloy fragments, and post-precipitates from the dissolver solution. The sludge deposited on the dissolver causes difficulties such as pipe clogging. The characteristics of the sludge collected from the dissolver vessels, which affect the reprocessing operation, were revealed through chemical composition analysis using ICP-AES, and XRD. It was confirmed that the major component of the sludge was zirconium molybdate, and no significant differences between ATR-MOX and ATR-UO$$_{2}$$ fuels were observed in terms of the sludge compositions. In order to gain further understanding of the properties of the sludge, the distributions of Pu and other trace elements were EPMA.

Oral presentation

Three decades of forward steps and prospect in Tokai reprocessing plant, 3; Operation experience and improvement on the dissolution process and clarification process

Suzuki, Kazuyuki; Kikuchi, Hideki; Hata, Katsuro; Tanaka, Ken; Miyamoto, Masanori; Nakamura, Yoshinobu; Hayashi, Shinichiro

no journal, , 

no abstracts in English

Oral presentation

MOX reprocessing at TRP, 3; Characteristics of MOX dissolution

Hata, Katsuro; Suzuki, Kazuyuki; Kikuchi, Hideki; Kogawa, Takayuki; Nakamura, Yoshinobu; Hayashi, Shinichiro

no journal, , 

no abstracts in English

Oral presentation

Corrosion evaluation of the dissolver

Suzuki, Kazuyuki; Nakamura, Yoshinobu; Hikita, Keiichi; Kogawa, Takayuki; Hayashi, Shinichiro

no journal, , 

The reprocessing plant dissolves Spent Fuels and it is a process to attract U and Pu after the removal of the Fission Products. Because dissolver is a tank with boiling nitric acid, there is it in the severe corrosion environment. Corrosion environment of the heat transfer surface is the severest. Therefore, the dissolver is made in High Chrome Nickel Steel in consideration of corrosion resistance. This paper reports a supersonic wave measurement method and corrosion rate of the dissolver.

Oral presentation

Fundamental test for improved elements of pulsed filter

Suzuki, Kazuyuki; Nakamura, Yoshinobu; Miyoshi, Ryuta; Sugai, Eiji; Hayashi, Shinichiro; Uchida, Toshitsugu*

no journal, , 

The pulse filter used by the dissolution and clarification process of the Tokai Reprocessing Plant uses the sintering metal powder filter. As for the sintering metal powder filter, being jammed is easy to occur by sludge. The basic examination of the sintering laminating wire mesh filter for the sintering metal powder filter was carried out.

Oral presentation

Development of the washing device for dissolver, 1; Development of high-pressure water washing device

Hikita, Keiichi; Uchida, Naoki; Suzuki, Kazuyuki; Mitani, Hironobu; Hata, Katsuro; Hayashi, Shinichiro; Yudo, Mitsuhiro*; Sakai, Hideaki*

no journal, , 

TRP dissolver deposits dissolver sludge which consists of zircaloy swarf with shearing operation and undissolved fission products such as Mo, Ru, Rh and Pd with dissolution operation. We have developed dissolver cleaning device which can be introduced through a ventilation pipe to inside dissolver.

Oral presentation

Filtration performance test for improved elements of pulsed filter

Hata, Katsuro; Suzuki, Kazuyuki; Miyoshi, Ryuta; Sugai, Eiji; Hikita, Keiichi; Nakamura, Yoshinobu; Hayashi, Shinichiro

no journal, , 

The pulse filter of the clarification process used the sintered metal powder filter at Tokai reprocessing plant. It is known that the sintered metal powder filter is easy to be clogged up by sludge. Therefore, we examined the filtration performance of the sintered laminated wire mesh filter which might substitute for the sintered metal powder filter.

Oral presentation

Plutonium concentration conditioning method of dissolution liquor in reprocessing of MOX fuel of Fugen reactor

Kikuchi, Hideki; Suzuki, Kazuyuki; Sugai, Eiji; Hikita, Keiichi; Otani, Takehisa; Samoto, Hirotaka; Hayashi, Shinichiro

no journal, , 

About 6t the Fugen MOX type B fuels, whose Pu content rate is about 1.7%, were reprocessed on Tokai Reprosessing Plant(TRP) to the present. It was required to control plutonium(Pu) concentration of dissolution liquor because of the higher Pu content of the MOX fuels. There operational method to control Pu concentration by dilution has be established. And the amount of Pu, which was transferred to the highly radioactive liquid waste system with the residue from the clarification process, was investigated.

Oral presentation

Replacement of butterfly valves installed in shearing off-gas treatment process of TRP, 2; Survey results of replaced valves

Sugai, Eiji; Kikuchi, Hideki; Hatanaka, Akira; Otani, Takehisa; Suzuki, Kazuyuki; Taguchi, Katsuya

no journal, , 

no abstracts in English

Oral presentation

Investigation of release characteristics of Kr gas arising in the reprocessing process

Otani, Takehisa; Suzuki, Kazuyuki; Hata, Katsuro; Kikuchi, Hideki; Nakamura, Daishi; Samoto, Hirotaka; Tanaka, Yukiyoshi

no journal, , 

The investigation of the behavior of krypton gas arising due to reprocessing of spent fuels has been performed at TRP. The whole amount of Kr gas transfers to the off-gas system through shearing and dissolution process, so it is applicable as an indicator to determine the progress of fuel dissolution. It is thought that the behavior of gaseous fission product, including Kr, in the spent fuels depends on burn-up and the type of spent fuels. In the reprocessing process, these deference are reflected to the migration rate of krypton gas between shearing off-gas system (SOG) and dissolver off-gas system (DOG). At TRP, four types of spent fuels (LWR; PWR, BWR and ATR; UO$$_{2}$$, MOX) were treated and examined about their release characteristics of krypton gas in order to understand the effect on burn-up and type of spent fuels. In this report, the results concerning the ATR-UO$$_{2}$$ fuel and ATR-MOX fuel are discussed compared with the results of LWR fuel.

Oral presentation

Maintenance of valves in dissolving solution environment at Tokai Reprocessing Plant

Kikuchi, Hideki; Numata, Shinji; Suzuki, Kazuyuki; Wakimoto, Fumitsugu; Tanaka, Yukiyoshi

no journal, , 

Tokai Reprocess Plant (TRP) has reprocessed about 1140 tU spent nuclear fuel for 35 years. In clarification process, there are 2 kinds of valves that used under spent fuel dissolving solution environment. These valves operation data are very valuable in process handling dissolving solution because the valves are rarely used in this process. In this report, we summarize malfunctions of the valves that we have experienced until now, and explain the method of maintenance and operation management.

Oral presentation

Clean-up activity of spent fuel powder (UO$$_{2}$$ powder) in mechanical treatment cell at Tokai Reprocessing Plant

Furuuchi, Yuta; Sato, Shinji; Yatabe, Hitoshi; Yokota, Satoru; Yamada, Takashi; Yahagi, Fumio; Terunuma, Hirotaka; Tokoro, Takeshi; Takahashi, Akihiro; Iijima, Shizuka; et al.

no journal, , 

Clean-up activity of spent fuel powder (UO$$_{2}$$ powder) in mechanical treatment cell was performed for the purpose of the preparation of decommissioning at TRP. For the clean-up activity, we selected an inexpensive vacuum cleaner and made tools, that was improved taking into account of use by means of a crane or a manipulator in the high dose cell, and applied it after a mock-up test. We report our experience and knowledge provided through this clean-up activity.

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