JOPSS - Search Results

Oral presentation

Development of portable radiation dose rate meter for domestic uses

Tanimura, Yoshihiko; Birumachi, Atsushi

no journal, ,

no abstracts in English

Oral presentation

Evaluation on irradiation behavior of ODS ferritic steels for high-burnup fuel cladding tubes

Yamashita, Shinichiro

no journal, ,

no abstracts in English

Oral presentation

Deuterium depth profiling in JT-60 divertor tiles

Hayashi, Takao; Masaki, Kei; Arai, Takashi; Miya, Naoyuki

no journal, ,

no abstracts in English

Oral presentation

Biosphere modelling for safety assessment of geological disposal taking account of evolution of surface environment

Kato, Tomoko; Suzuki, Yuji*; Oi, Takao

no journal, ,

no abstracts in English

Oral presentation

Simulation for examining microbial effect for safety assessment of geological disposal

Tochigi, Yoshikatsu

no journal, ,

no abstracts in English

Oral presentation

Development of a long-life vitrification melter

Kato, Junya; Miyauchi, Atsushi; Yamasaki, Akito*

no journal, ,

no abstracts in English

Oral presentation

U, Pu and Np co-recovery in NEXT process

Nakahara, Masaumi; Sano, Yuichi; Nomura, Kazunori

no journal, ,

Concerning the advance aqueous reprocessing system named NEXT process, the simplified solvent extraction process was conducted for U, Pu and Np co-recovery in JAEA. In this study, the feed solution or scrubbing solution were adjusted to high nitric acid concentration, which the extraction and oxidation behavior of Np were estimated using the dissolver solution of irradiated fast reactor fuel. These experimental results showed the large contribution of nitric acid concentration at the extraction section to Np oxidation and extraction, and the effectiveness of high nitric acid concentration in the feed solution, which might bring the acceleration of the Np oxidation in the feed solution as well as at the extraction section in the centrifugal contactors.

Oral presentation

Development of risk communication training program for risk communicators in the Japan nuclear field

Gunji, Ikuko; Tabata, Rimiko; Otoshi, Sachio*; Kuwagaki, Reiko*; Ishibashi, Yoichiro*

no journal, ,

no abstracts in English

Oral presentation

Determination of neptunium of Tokai reprocessing plant; Determination of neptunium by spectrometry in nitric acid media

Kitao, Takahiko; Nemoto, Hirokazu*; Yamada, Keiji; Sakai, Toshio

no journal, ,

no abstracts in English

Oral presentation

Development of a nondestructive degradation evaluation method before crack initiation for the austenitic stainless steel

Takaya, Shigeru; Nagae, Yuji

no journal, ,

no abstracts in English

Oral presentation

Developments of short process technology of plutonium examination about developments of improving fluidity of the powder for MOX fuel

Mukai, Yasunobu; Kato, Yoshiyuki; Kimura, Yuichi*; Nemoto, Ryo*

no journal, ,

no abstracts in English

Oral presentation

Improvement of corrosion resistance of equipment material for dry reprocessing by ceramic coating technology

Arai, Yoichi; Takeuchi, Masayuki; Kato, Toshihiro*

no journal, ,

no abstracts in English

Oral presentation

The Investigation of stability and surface characteristics on SO $_{3}$ decomposition catalyst for thermo chemical hydrogen production IS process

Imai, Yoshiyuki

no journal, ,

no abstracts in English

Oral presentation

Present status and future plan of HTTR (High Temperature Engineering Test Reactor) fuel temperature estimation

Tochio, Daisuke; Inoi, Hiroyuki

no journal, ,

no abstracts in English

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Development of portable radiation dose rate meter for domestic uses

Evaluation on irradiation behavior of ODS ferritic steels for high-burnup fuel cladding tubes

Deuterium depth profiling in JT-60 divertor tiles

Biosphere modelling for safety assessment of geological disposal taking account of evolution of surface environment

Simulation for examining microbial effect for safety assessment of geological disposal

Development of a long-life vitrification melter

U, Pu and Np co-recovery in NEXT process

Development of risk communication training program for risk communicators in the Japan nuclear field

Determination of neptunium of Tokai reprocessing plant; Determination of neptunium by spectrometry in nitric acid media

Development of a nondestructive degradation evaluation method before crack initiation for the austenitic stainless steel

Developments of short process technology of plutonium examination about developments of improving fluidity of the powder for MOX fuel

Improvement of corrosion resistance of equipment material for dry reprocessing by ceramic coating technology

The Investigation of stability and surface characteristics on SO $_{3}$ decomposition catalyst for thermo chemical hydrogen production IS process

Present status and future plan of HTTR (High Temperature Engineering Test Reactor) fuel temperature estimation