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Maekawa, Fujio; Takei, Hayanori
Purazuma, Kaku Yugo Gakkai-Shi, 98(5), p.206 - 210, 2022/05
In developing an accelerator-driven nuclear transmutation system (ADS), it is necessary to solve technical issues related to proton beams, such as the development of materials that can withstand high-intensity proton beams and the characterization of subcritical cores driven by proton beams. Therefore, at the high-intensity proton accelerator facility J-PARC, a transmutation experimental facility that actually conducts various tests using a high-intensity proton beam is being planned. This paper introduces the outline and future direction of the transmutation experimental facility.
Oigawa, Hiroyuki; Sasa, Toshinobu; Kikuchi, Kenji; Nishihara, Kenji; Kurata, Yuji; Umeno, Makoto*; Tsujimoto, Kazufumi; Saito, Shigeru; Futakawa, Masatoshi; Mizumoto, Motoharu; et al.
Proceedings of 4th International Workshop on the Utilisation and Reliability of High Power Proton Accelerators, p.507 - 517, 2005/11
Under the framework of J-PARC, the Japan Atomic Energy Research Institute (JAERI) plans to construct the Transmutation Experimental Facility (TEF). The TEF consists of two facilities: the Transmutation Physics Experimental Facility (TEF-P) and the ADS Target Test Facility (TEF-T). The TEF-P is a critical facility which can accept a 600 MeV - 10 W proton beam. The TEF-T is a material irradiation facility using a 600 MeV - 200 kW proton beam, where a Pb-Bi target is installed, but neutron multiplication by nuclear fuel will not be attempted. This report describes the purposes of the facility, the present status of the conceptual design, and the expected experiments to be performed.
Fusion Neutron Laboratory
JAERI-Review 2004-017, 163 Pages, 2004/07
JAERI-Review-2004-017.pdf:25.47MB
no abstracts in English
Enoeda, Mikio
JAERI-Conf 2004-012, 237 Pages, 2004/07
JAERI-Conf-2004-012.pdf:44.1MB
This report is the Proceedings of "the Eleventh International Workshop on Ceramic Breeder Blanket Interactions" which was held as a workshop on ceramic breeders Under the IEA Implementing Agreement on the Nuclear Technology of Fusion Reactors, and the Japan-US Fusion Collaboration Framework. In the workshop, information exchange was performed for designs of solid breeder blankets and test blankets in EU, Russia and Japan, recent results of irradiation tests, HICU, EXOTIC-8 and the irradiation tests by IVV-2M, modeling study on tritium release behavior of Li
TiO
and other breeders, fabrication technology developments and characterization of the LiTiO and Li
SiO pebbles, research on measurements and modeling of thermo-mechanical behaviors of LiTiO and LiSiO pebbles, and interfacing issues, such as, fabrication technology for blanket box structure, neutronics experiments of blanket mockups by fusion neutron source and tritium recovery system.
Research Committee on Reactor Physics
JAERI-Research 2004-004, 409 Pages, 2004/03
JAERI-Research-2004-004.pdf:28.53MB
This report summarizes the second phase (FY2001-2002) activity of "the Working Party (WP) on Reactor Physics for LWR Next Generation Fuels". The next generation fuels mean the ones aiming at further extended burn-up such as 70GWd/t over the current design. In the WP, the benchmark activity has been conducted to investigate and improve the calculation accuracy of the nuclear characteristics of the next generation fuels. In the second phase activity, all benchmark results were compiled and compared. Based on the comparison, the present status of calculation accuracy for the next generation fuels has been confirmed, and the factors causing the calculation differences were analyzed in detail. Moreover, analyses of the post irradiation and critical experiments with the codes used in the benchmark were reviewed, and future experiments and research subjects necessary to reduce the calculation differences were discussed and proposed.
Sato, Satoshi; Morioka, Atsuhiko; Kinno, Masaharu*; Ochiai, Kentaro; Hori, Junichi; Nishitani, Takeo
Journal of Nuclear Science and Technology, 41(Suppl.4), p.66 - 69, 2004/03
no abstracts in English
Baba, Shinichi; Ishihara, Masahiro; Sozawa, Shizuo; Sekino, Hajime
JAERI-Data/Code 2003-003, 394 Pages, 2003/03
JAERI-Data-Code-2003-003.pdf:13.63MB
The research on the radiation damage mechanism of heat resistant ceramic composite materials is one of the research subjects of the innovative basic research in the field of high temperature engineering, using the High Temperature engineering Test Reactor (HTTR). Three series of irradiation tests on the heat resistant ceramic composite materials, first to third irradiation test program, were carried out using the Japan Material Testing Reactor (JMTR). This is a summary report on the the first irradiation test program; irradiation induced dimensional change, thermal expansion coefficient, X-ray diffraction and 
-ray spectrum are reported.
Matsushita, Akira*; Yamamoto, Tetsuya*; Matsumura, Akira*; Shibata, Yasushi*; Nose, Tadao*; Yamamoto, Kazuyoshi; Kumada, Hiroaki; Hori, Naohiko; Torii, Yoshiya
Proceedings of 9th International Symposium on Neutron Capture Therapy for Cancer, p.203 - 204, 2000/10
no abstracts in English
Nagao, Yoshiharu; Nakamichi, Masaru; Kawamura, Hiroshi
Journal of Nuclear Science and Technology, 37(Suppl.1), p.423 - 426, 2000/03
no abstracts in English
Okumura, Keisuke; Mori, Takamasa; Nakagawa, Masayuki; Kaneko, Kunio*
Journal of Nuclear Science and Technology, 37(2), p.128 - 138, 2000/02
no abstracts in English
Iwase, Akihiro
Materia, 37(6), p.470 - 478, 1998/00
no abstracts in English
March 31, 1993JAERI-M 93-226, 229 Pages, 1993/12
no abstracts in English
Nomura, Yasushi; ;
JAERI-M 92-163, 66 Pages, 1992/11
no abstracts in English
Kaku Nenryo, (13), p.19 - 20, 1990/05
no abstracts in English
;
JAERI-M 7520, 29 Pages, 1978/02
no abstracts in English
Sawa, Kazuhiro*; Haseda, Masaya*; Aihara, Jun
no journal, ,
In high temperature gas-cooled reactors (HTGRs), Tri-isotropic (TRISO)-coated fuel particles are employed as fuel. In the high burnup coated fuel particle, stress due to fission gas pressure and irradiation-induced pyrolytic carbon (PyC) shrinkage is introduced into the coating layers and consequently the stress could cause failure of coating layers under high burnup irradiation condition. A failure model has developed to predict failure fraction of TRISO-coated particle under high burnup irradiation. In the model, failure probability is strongly dependent on the irradiation characteristics of PyC. This paper describes the outline of the failure model and evaluation result of high burnup fuel irradiation experiment by the model.
