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Journal Articles

Study on immobilization technology of radioactive krypton gas by ion-implantation and sputtering process

Samoto, Hirotaka; Kimura, Norimichi; Otani, Takehisa; Sugai, Eiji; Hayashi, Shinichiro

Proceedings of International Conference on Advanced Nuclear Fuel Cycle; Sustainable Options & Industrial Perspectives (Global 2009) (CD-ROM), p.458 - 463, 2009/09

JAEA has been developing technology to immobilize radioactive krypton gas to metal alloy by ion-implantation method as a stable storage technique of krypton gas recovered from a reprocessing plant. The characteristics of implantation of krypton gas and of krypton implanted alloy were investigated by the cold test performed so far. In this paper, we report the results of the hot immobilization test performed at the Krypton Recovery development Facility (hereafter called KRF) which is attached to the Tokai Reprocessing Plant (hereafter called TRP). In this test, we immobilized the radioactive krypton gas recovered from TRP by cryogenic distillation process of KRF and investigated the gas retention characteristics of the implanted alloy.

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

Studies on krypton immobilization technology using ion-implantation and sputtering process, 19; Retention characteristic of radioactive Kr immobilized alloy

Samoto, Hirotaka; Kimura, Norimichi; Otani, Takehisa; Sugai, Eiji; Takahashi, Makoto; Hayashi, Shinichiro; Akutsu, Tomoyuki*

no journal, , 

Krypton is immobilized to metal alloy by ion-implantation and sputtering process. The retention characteristic of immobilized radioactive Kr with different storage temperature of the metal alloy is reported.

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

Dissolution test on the sludge of the dissolver

Sugai, Eiji; Terunuma, Hirotaka; Otani, Takehisa; Hikita, Keiichi; Hatanaka, Akira; Samoto, Hirotaka; Okano, Masanori; Hayashi, Shinichiro

no journal, , 

A dissolution test of the sludge gathered from the dissolver of Tokai Reprocessing Plant (TRP) was performed for the purpose of eliminating of the sludge, which deposited in the dissolver and clogged pipes equipped in the dissolver. In the result, the sludge consisted primarily of ZrMo$$_{2}$$O$$_{7}$$(OH)$$_{2}$$(H$$_{2}$$O)$$_{2}$$ and was possible to eliminate at the rate of about 80% by using NaOH and HNO$$_{3}$$ reagent which was commonly-used in the PUREX process. From this experimental result, it is thought that the method of using NaOH and HNO$$_{3}$$ reagent is effective method for the elimination of the sludge which deposited in the dissolver.

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

Removal technologies for the sludge arising in dissolver due to reprocessing at Tokai Reprocessing Plant

Sugai, Eiji; Hata, Katsuro; Kikuchi, Hideki; Terunuma, Hirotaka; Uchida, Naoki; Taguchi, Katsuya

no journal, , 

no abstracts in English

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