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Journal Articles

Present status of J-PARC linac

Oguri, Hidetomo; Hasegawa, Kazuo; Ito, Takashi; Chishiro, Etsuji; Hirano, Koichiro; Morishita, Takatoshi; Shinozaki, Shinichi; Ao, Hiroyuki; Okoshi, Kiyonori; Kondo, Yasuhiro; et al.

Proceedings of 11th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.389 - 393, 2014/10

no abstracts in English

Journal Articles

None

Usami, Isao

Saikuru Kiko Giho, (11), p.7 - 18, 2001/06

None

Journal Articles

THE REACTION RATEN DISTRIBUTION MEASUREMENT AND THE CORE PERFORMANCEEVALUATION IN THE PROTOTYPE FBR MONJU

Usami, Isao; ; Nakashima, Fumiaki;

Proceedings of 9th International Conference on Nuclear Engineering (ICONE-9) (CD-ROM), 0 Pages, 2001/00

None

Journal Articles

Reaction rate distribution measurement and the core performance evaluation in the prototype FBR Monju

Usami, Isao; Suzuoki, Zenro; ; Nakashima, Fumiaki

Proceedings of 9th International Conference on Nuclear Engineering (ICONE-9) (CD-ROM), 0 Pages, 2001/00

None

Journal Articles

APPLICABILITY OF THE 3D TRANSPORT CODE TORT THE SHIELDING ANALYSIS OF THE REACTOR CAVITY SHIELDING FLOOR IN THE PROTOTYPE FBR MONJU

; Usami, Isao; *

Proceedings of International Conference on the Physics of Reactors (PHYSOR 2000), 0 Pages, 2000/00

None

Journal Articles

MEASUREMENT OF SHIELDING CHARACTERISTICS IN THE PROTOTYPE FBR MONJU

Usami, Isao

Dai-9-Kai Hoshasen Shahei Kokusai Kaigi, 0 Pages, 1999/00

None

Journal Articles

None

Ito, Chikara; Aoyama, Takafumi; Usami, Isao

Genshiryoku eye, 45(1), p.55 - 59, 1999/00

None

Journal Articles

The Reaction rate distribution measurements by the foil activation method in the prototype FBR Monju

Usami, Isao; ; Nakashima, Fumiaki

Proceedings of 9th International Symposium on Reactor Dosimetry (ISRD-9), p.865 - 872, 1999/00

None

Journal Articles

Reactor physics measurements at start-up of MONJU

Nakashima, Fumiaki; ; Usami, Isao; ; ; 2 of others*

Proceedings of International Conference on the Physics of Reactors (PHYSOR '96), E-76- Pages, 1996/00

None

Oral presentation

Development of high-level liquid waste conditioning technology for advanced nuclear fuel cycle, 19; Dependence of dissolution rate of insoluble residue on its composition

Usami, Tsuyoshi*; Tsukada, Takeshi*; Yamagishi, Isao; Morita, Yasuji

no journal, , 

Development of high-level liquid waste (HLW) conditioning technology for advanced nuclear fuel cycle was conducted for the purpose of the reduction of potential problems in the verification process for HLW. It includes development of separation technology for Mo, Pd and Ru from HLW and development of separate treatment of the insoluble residue. To evaluate characteristics of the insoluble residue, simulated residue of metal alloy composed of Ru, Mo, Rh and Pd was dissolved with heated nitric acid. The results showed that higher concentration of Pd in the alloy makes the alloy easier to be dissolved, and higher concentration of Ru makes the alloy more difficult to be dissolved.

Oral presentation

Development of high-level liquid waste conditioning technology for advanced nuclear fuel cycle, 21; Overall results and evaluation

Morita, Yasuji; Yamagishi, Isao; Sato, Soichi; Kirishima, Akira*; Fujii, Toshiyuki*; Uehara, Akihiro*; Tsukada, Takeshi*; Usami, Tsuyoshi*; Kurosaki, Ken*

no journal, , 

Development of high-level liquid waste (HLW) conditioning technology for advanced nuclear fuel cycle was conducted for the purpose of the reduction of potential problems in the verification process for HLW. It includes development of separation technology for Mo, Pd and Ru from HLW and development of separate treatment of the insoluble residue. The present report gives the overall results of the research and development and their evaluation. For the Mo separation, the extraction process with HDEHP was developed by performing continuous extraction tests and process simulation by a calculation code. An extraction process for Pd by 5,8-diethyl-7-hydroxy-6-dodecanone oxime was also developed, but was evaluated as less mature than the HEDHP process. As Ru separation method, volatilization of RuO$$_{4}$$ after electrochemical oxidation was examined. Dissolution residue (metal alloy) and recovered Pd and Ru were solidified together by hot-press method.

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