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Journal Articles

Study on the effect of long-term high temperature irradiation on TRISO fuel

Shaimerdenov, A.*; Gizatulin, S.*; Dyussambayev, D.*; Askerbekov, S.*; Ueta, Shohei; Aihara, Jun; Shibata, Taiju; Sakaba, Nariaki

Nuclear Engineering and Technology, 54(8), p.2792 - 2800, 2022/08

 Times Cited Count:8 Percentile:82.31(Nuclear Science & Technology)

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

Integrity confirmation tests and post-irradiation test plan of the HTTR first-loading fuel

Sawa, Kazuhiro; Sumita, Junya; Ueta, Shohei; Suzuki, Shuichi*; Tobita, Tsutomu*; Saito, Takashi; Minato, Kazuo; Koya, Toshio; Sekino, Hajime

Journal of Nuclear Science and Technology, 38(6), p.403 - 410, 2001/06

 Times Cited Count:7 Percentile:48.18(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Fabrication of the first-loading-fuel of the High Temperature engineering Test Reactor

Sawa, Kazuhiro; Tobita, Tsutomu*; Mogi, Haruyoshi; Shiozawa, Shusaku; Yoshimuta, Shigeharu*; Suzuki, Shuichi*;

Journal of Nuclear Science and Technology, 36(8), p.683 - 690, 1999/08

 Times Cited Count:32 Percentile:88.99(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Advanced coatings for HTGR fuel particles against corrosion of SiC layer

Minato, Kazuo; Fukuda, Kosaku; Ishikawa, Akiyoshi; Mita, Naoaki

Journal of Nuclear Materials, 246(2-3), p.215 - 222, 1997/00

 Times Cited Count:16 Percentile:75.26(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Experimental data report for test TS-5; Reactivity initiated accident test in the NSRR with pre-irradiated BWR fuel rod

Nakamura, Takehiko; ; Ishijima, Kiyomi; ; Yamahara, Takeshi; ; Ito, Tadaharu

JAERI-Research 95-080, 92 Pages, 1995/11

JAERI-Research-95-080.pdf:8.22MB

no abstracts in English

JAEA Reports

Experimental data report for test TS-4, Reactivity initiated accident test in the NSRR with pre-irradiated BWR fuel rod

Nakamura, Takehiko; ; Sobajima, Makoto; Ishijima, Kiyomi; ; Yamahara, Takeshi; ; Kikuchi, Teruo

JAERI-M 94-030, 103 Pages, 1994/03

JAERI-M-94-030.pdf:10.15MB

no abstracts in English

JAEA Reports

Experimental data report for test TS-3; Reactivity initiated accident test in the NSRR with pre-irradiated BWR fuel rod

Nakamura, Takehiko; ; Sobajima, Makoto; ; ; Yamahara, Takeshi; ; Kikuchi, Teruo

JAERI-M 93-183, 115 Pages, 1993/09

JAERI-M-93-183.pdf:13.73MB

no abstracts in English

JAEA Reports

Experimental data report for test TS-2; Reactivity initiated accident test in NSRR with pre-irradiated BWR fuel rod

Nakamura, Takehiko; ; Sobajima, Makoto; ; ; Yamahara, Takeshi; ; Kikuchi, Teruo

JAERI-M 93-006, 101 Pages, 1993/02

JAERI-M-93-006.pdf:11.47MB

no abstracts in English

JAEA Reports

Development of plastic capsule for research reactor irradiation

Arigane, Kenji; ; ; Aoyama, Isao; Seguchi, Tadao; Takahashi, Hidetake

JAERI-M 92-078, 22 Pages, 1992/06

JAERI-M-92-078.pdf:0.75MB

no abstracts in English

Journal Articles

Research and development of HTTR coated particle fuel

Fukuda, Kosaku; Ogawa, Toru; Hayashi, Kimio; Shiozawa, Shusaku; Tsuruta, Harumichi; ; ; ;

Journal of Nuclear Science and Technology, 28(6), p.570 - 581, 1991/06

no abstracts in English

JAEA Reports

Irradiation performance and integrity of thorium oxide based coated particle fuels at high burnups

Shiratori, Tetsuo; Akabori, Mitsuo; Fukuda, Kosaku; Tsuruta, Harumichi

JAERI-M 90-144, 64 Pages, 1990/09

JAERI-M-90-144.pdf:6.75MB

no abstracts in English

Journal Articles

Irradiation experiments of VHTR reference fuels by an in-pile gas loop(OGL-1)

; ; ; Minato, Kazuo; ; Ikawa, Katsuichi

Nihon Genshiryoku Gakkai-Shi, 26(1), p.57 - 74, 1984/00

 Times Cited Count:1 Percentile:18.98(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

FREC-4A : A Computer Program to Predict Fuel Rod Performance under Normal Reactor Operation

Harayama, Yasuo;

JAERI-M 9683, 140 Pages, 1981/10

JAERI-M-9683.pdf:3.19MB

no abstracts in English

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

Oral presentation

Overview of ATF R&D program in Japan

Yamashita, Shinichiro; Mohamad, A. B.; Ioka, Ikuo; Nemoto, Yoshiyuki; Kawanishi, Tomohiro; Osaka, Masahiko; Kaji, Yoshiyuki

no journal, , 

After the nuclear accident at Fukushima Daiichi power plant, global interest has expanded in exploring fuels with enhanced performance during severe accident, and enhancing the accident tolerance of light water reactors (LWRs) became a topic of serious discussion all over the world. In Japan, research and development (R&D) program for establishing technical basis of ATF has been conducted by JAEA in cooperation with power plant providers, fuel venders and universities. In this presentation, the overview of ATF R&D program in Japan will be introduced with the explanation on JAEA's role in ATF R&D program including the recent result from fundamental ATF studies.

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