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Sawa, Kazuhiro; Ueta, Shohei
Nuclear Engineering and Design, 233(1-3), p.163 - 172, 2004/10
Times Cited Count:59 Percentile:95.36(Nuclear Science & Technology)In the high temperature gas-cooled reactors (HTGRs), refractory coated fuel particles are employed as fuel to permit high outlet coolant temperature. The High Temperature Engineering Test Reactor (HTTR) employs Tri-isotropic (Triso) coated fuel particles in the prismatic fuel assembly. Research and development on the HTTR fuel has been carried out spread over about 30 years, in fuel fabrication technologies, fuel performance, and so on. Furthermore, for upgrading of HTGR technologies, an extended burnup TRISO-coated fuel particle and an advanced type of coated fuel particle, ZrC-coated fuel particle in order to keep the integrity at higher operating temperatures has been developed. The present paper provides experiences and current status of research and development works for the HTGR fuel in the HTTR Project.
Enoeda, Mikio
JAERI-Conf 2004-012, 237 Pages, 2004/07
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 LiTiO and other breeders, fabrication technology developments and characterization of the LiTiO and LiSiO 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.
Nakata, Tetsuo*; Katanishi, Shoji; Takada, Shoji; Yan, X.; Kunitomi, Kazuhiko
Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(4), p.478 - 489, 2003/12
no abstracts in English
Takeda, Takeshi; Nakagawa, Shigeaki; Kunitomi, Kazuhiko
Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00
no abstracts in English
A.Saltelli*; T.H.Andres*; Homma, Toshimitsu
Computational Statistics & Data Analysis, 20, p.387 - 407, 1995/00
Times Cited Count:42 Percentile:89.63(Computer Science, Interdisciplinary Applications)no abstracts in English
Kyoya, Masahiko; ; Kusunoki, Tsuyoshi; *; Takahashi, Teruo*
JAERI-M 94-079, 116 Pages, 1994/06
no abstracts in English
; ; *; *; *; *; *; *
JAERI-M 85-182, 304 Pages, 1985/11
no abstracts in English
;
JAERI-M 82-132, 481 Pages, 1982/10
no abstracts in English
;
JAERI-M 9629, 274 Pages, 1981/08
no abstracts in English
; ; ;
JAERI-M 8947, 420 Pages, 1980/07
no abstracts in English
; ; ; ; ; ;
JAERI-M 8400, 222 Pages, 1979/09
no abstracts in English
Genshiryoku Kogyo, 23(2), p.35 - 41, 1977/02
no abstracts in English
Nuclear Instruments and Methods, 143(2), p.267 - 271, 1977/02
no abstracts in English
; ; ; ; ; ; ; ; ; ; et al.
JAERI-M 6895, 170 Pages, 1976/12
no abstracts in English
Hatanaka, Koichiro
no journal, ,
JAEA has initiated research and development of spent fuel direct disposal in FY 2013. In the research and development so far, we were able to construct approaches for design and safety assessment and to present the disposal concept based on multi barrier system as well as the technical level of the direct disposal, through carrying out the preliminary design and safety assessment, by taking characteristics of geological environment in Japan and the spent fuels into consideration. In addition, challenges/issues related to the design and safety assessment to be addressed towards the research and development in the next stage, were identified, classified and organized. In the future, we are going to present the technical reliability of the direct disposal by resolving the challenges/issues.