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Nomoto, Yasunobu; Mizuta, Naoki; Morita, Keisuke; Aoki, Takeshi; Okita, Shoichiro; Ishii, Katsunori; Kurahayashi, Kaoru; Yasuda, Takanori; Tanaka, Masato; Isaka, Kazuyoshi; et al.
Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 7 Pages, 2023/05
Sector of Fast Reactor and Advanced Reactor Research and Development
JAEA-Evaluation 2020-001, 128 Pages, 2020/08
Japan Atomic Energy Agency consulted with the "Evaluation Committee of Research Activities for High Temperature Gas-cooled Reactor (hereinafter referred to as "HTGR") and Related Hydrogen Production Technology" (hereinafter referred to as "Evaluation Committee"), which consists of specialists in the fields of the evaluation subjects of high temperature gas-cooled reactor and related heat application technology, for interim assessment in the 3rd Mid-and Long-Term Plan about the relevance of the management and research activities of the HTGR and related application technology during the period from April 2017 to March 2020. As a result, three members of the Evaluation Committee concluded a score of "S", and seven members of the Evaluation Committee concluded a score of "A". The interim assessment to research and development activities from April 2017 to March 2020 was concluded a score of "A". In addition, the Evaluation Committee recommended that the judgement to move to the construction phase of the HTTR-heat utilization test plant be made after 2 years, after the HTTR will be restarted and the thermal load fluctuation tests using HTTR will be carried out. This report lists the members of the Evaluation Committee and outlines the assessment item and the review process for procedure of the assessment. The assessment report which was issued by the Evaluation Committee is attached.
Nishihara, Tetsuo; Yan, X.; Tachibana, Yukio; Shibata, Taiju; Ohashi, Hirofumi; Kubo, Shinji; Inaba, Yoshitomo; Nakagawa, Shigeaki; Goto, Minoru; Ueta, Shohei; et al.
JAEA-Technology 2018-004, 182 Pages, 2018/07
Research and development on High Temperature Gas-cooled Reactor (HTGR) in Japan started since late 1960s. Japan Atomic Energy Agency (JAEA) in cooperation with Japanese industries has researched and developed system design, fuel, graphite, metallic material, reactor engineering, high temperature components, high temperature irradiation and post irradiation test of fuel and graphite, high temperature heat application and so on. Construction of the first Japanese HTGR, High Temperature engineering Test Reactor (HTTR), started in 1990. HTTR achieved first criticality in 1998. After that, various test operations have been carried out to establish the Japanese HTGR technologies and to verify the inherent safety features of HTGR. This report presents several system design of HTGR, the world-highest-level Japanese HTGR technologies, JAEA's knowledge obtained from construction, operation and management of HTTR and heat application technologies for HTGR.
Kunitomi, Kazuhiko; Nishihara, Tetsuo; Yan, X.; Tachibana, Yukio; Shibata, Taiju
Nihon Genshiryoku Gakkai-Shi ATOMO, 60(4), p.236 - 240, 2018/04
High temperature gas-cooled reactor (HTGR) is a graphite-moderated and helium-gas-cooled thermal-neutron reactor that has excellent safety features and can produce high temperature heat of 950C. It is expected to use for various heat applications as well as for electricity generation to reduce carbon dioxide emission. Japan Atomic Energy Agency (JAEA) has been promoted research and development to demonstrate the HTGR safety features using High temperature engineering test reactor (HTTR) and it's heat application. JAEA are also conducting the action to international deployment of Japanese HTGR technologies in cooperation with industries-government-academia. This paper reports status of the research and development of HTGR and domestic and international collaborations.
Shiozawa, Shusaku; Komori, Yoshihiro; Ogawa, Masuro
Nihon Genshiryoku Gakkai-Shi, 47(5), p.342 - 349, 2005/05
For the purpose to extend high temperature nuclear heat application, JAERI constructed the HTTR, High Temperature Engineering Test Reactor, and has carried out research and development of high temperature gas cooled reactor system aiming at high efficiency power generation and hydrogen production. This paper explains the history, main results, present status of research and development of HTTR project, international cooperation of research and development of HTGR and future plan aiming at development of Japanese original future HTGR-Hydrogen production system. This paper includes results from the study, which is entrusted from Ministry of Education, Culture, Sports, Science and Technology of Japan.
Shiozawa, Shusaku
Kiho Enerugi Sogo Kogaku, 24(1), p.40 - 53, 2001/04
no abstracts in English
Inaba, Yoshitomo; Fumizawa, Motoo; Hishida, Makoto; Ogawa, Masuro; Aritomi, Masanori*; Kozaki, Yasutsugu*; *; *; *; *; et al.
JAERI-Tech 96-019, 122 Pages, 1996/05
no abstracts in English
Inaba, Yoshitomo; Fumizawa, Motoo; Hishida, Makoto; Ogawa, Masuro; ; Aritomi, Masanori*; Kozaki, Yasutsugu*; *; *; *; et al.
JAERI-Review 96-007, 87 Pages, 1996/05
no abstracts in English
Baba, Osamu
Sci. Technol. Jpn., 15(58), p.7 - 9, 1996/00
no abstracts in English
Saito, Shinzo
Gensan Semina "Koon Gasuro Kaihatsu To Netsu Riyo Gijutsu No Tembo", p.1 - 10, 1992/02
no abstracts in English
Saito, Shinzo
Genshiryoku Kogyo, 38(1), p.24 - 30, 1992/01
no abstracts in English
Saito, Shinzo
Proc. of IEA Int. Conf. on Technology Responses to Global Environmental Challenges,Vol. l, p.393 - 396, 1991/00
no abstracts in English
Netsu Enerugi Shohi To Chikyu Kankyo Hogo No Hohoron, p.173 - 187, 1990/05
no abstracts in English
Nihon Genshiryoku Gakkai-Shi, 27(5), p.403 - 410, 1985/00
Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)no abstracts in English
; ;
Nihon Genshiryoku Gakkai-Shi, 25(12), p.971 - 978, 1983/00
Times Cited Count:1 Percentile:22.52(Nuclear Science & Technology)no abstracts in English
Nihon Genshiryoku Gakkai-Shi, 18(11), p.685 - 690, 1976/11
no abstracts in English
Inaba, Yoshitomo
no journal, ,
This presentation summarizes the features of HTGR concerning safety and heat application technologies, and the outline of HTGR development in JAEA.