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Journal Articles

Research and development on HTGR fuel in the HTTR project

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.

JAEA Reports

Proceedings of the 11th International Workshop on Ceramic Breeder Blanket Interactions; December 15 - 17, 2003, Tokyo, Japan

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$$_{2}$$TiO$$_{3}$$ and other breeders, fabrication technology developments and characterization of the Li$$_{2}$$TiO$$_{3}$$ and Li$$_{4}$$SiO$$_{4}$$ pebbles, research on measurements and modeling of thermo-mechanical behaviors of Li$$_{2}$$TiO$$_{3}$$ and Li$$_{4}$$SiO$$_{4}$$ 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.

Journal Articles

Nuclear, thermal and hydraulic design for Gas Turbine High Temperature Reactor (GTHTR300)

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

Journal Articles

Empirical modeling of pressure rise and power characteristics of helium circulators for the High Temperature engineering Test Reactor

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

Journal Articles

Sensitivity analysis of model output; Performance of the iterated fractional factorial design method

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

JAEA Reports

Performance evaluation of nuclear ship engineering simulation system

Kyoya, Masahiko; ; Kusunoki, Tsuyoshi; *; Takahashi, Teruo*

JAERI-M 94-079, 116 Pages, 1994/06

JAERI-M-94-079.pdf:3.19MB

no abstracts in English

JAEA Reports

Status and Future Studies of the IHX Design of the ex.VHTR

; ; *; *; *; *; *; *

JAERI-M 85-182, 304 Pages, 1985/11

JAERI-M-85-182.pdf:9.26MB

no abstracts in English

JAEA Reports

Data List of Nuclear Power Plants in Japan, 1981 Edition

;

JAERI-M 82-132, 481 Pages, 1982/10

JAERI-M-82-132.pdf:12.63MB

no abstracts in English

JAEA Reports

JAEA Reports

JAEA Reports

Design Studies on Irradiation-Bed Core of the Experimental Multi-Purpose VHTR

; ; ; ; ; ;

JAERI-M 8400, 222 Pages, 1979/09

JAERI-M-8400.pdf:5.71MB

no abstracts in English

Journal Articles

Increase in speed of ADC and Improvement of differential non-linearity

Genshiryoku Kogyo, 23(2), p.35 - 41, 1977/02

no abstracts in English

Journal Articles

Increase in speed of Wilkinson-type ADC and improvement of differential non-linearity

Nuclear Instruments and Methods, 143(2), p.267 - 271, 1977/02

no abstracts in English

JAEA Reports

Reference Core Design Mark-III for Experimental Multi-Purpose VHTR

; ; ; ; ; ; ; ; ; ; et al.

JAERI-M 6895, 170 Pages, 1976/12

JAERI-M-6895.pdf:5.49MB

no abstracts in English

Oral presentation

Outline of research and development of spent fuel direct disposal in Japan

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.

15 (Records 1-15 displayed on this page)
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