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JAEA Reports

Assessment report on research and development activities in FY2019; Activity "Research and development on high temperature gas-cooled reactor and related heat application technology" (Interim report)

Sector of Fast Reactor and Advanced Reactor Research and Development

JAEA-Evaluation 2020-001, 128 Pages, 2020/08

JAEA-Evaluation-2020-001.pdf:7.44MB

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.

JAEA Reports

Excellent feature of Japanese HTGR technologies

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

JAEA-Technology-2018-004.pdf:18.14MB

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.

Journal Articles

The Development status of Generation IV reactor systems, 2; High temperature gas-cooled reactor (HTGR)

Kunitomi, Kazuhiko; Nishihara, Tetsuo; Yan, X.; Tachibana, Yukio; Shibata, Taiju

Nippon Genshiryoku Gakkai-Shi, 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 950$$^{circ}$$C. 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.

Journal Articles

The HTTR project as the world leader of HTGR research and development

Shiozawa, Shusaku; Komori, Yoshihiro; Ogawa, Masuro

Nippon 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.

Journal Articles

The Characteristics, development status and perspective of HTGR as innovative reactor

Shiozawa, Shusaku

Kiho Enerugi Sogo Kogaku, 24(1), p.40 - 53, 2001/04

no abstracts in English

JAEA Reports

Basic study for development of nuclear heat application systems

Inaba, Yoshitomo; Fumizawa, Motoo; Hishida, Makoto; Ogawa, Masuro; Aritomi*; Kozaki, Yasutsugu*; *; *; *; *; et al.

JAERI-Tech 96-019, 122 Pages, 1996/05

JAERI-Tech-96-019.pdf:4.42MB

no abstracts in English

JAEA Reports

Present status and future perspective of nuclear heat application systems

Inaba, Yoshitomo; Fumizawa, Motoo; Hishida, Makoto; Ogawa, Masuro; ; Aritomi*; Kozaki, Yasutsugu*; *; *; *; et al.

JAERI-Review 96-007, 87 Pages, 1996/05

JAERI-Review-96-007.pdf:2.66MB

no abstracts in English

Journal Articles

High-temperature engineering test reactor (HTTR)

Baba, Osamu

Sci. Technol. Jpn., 15(58), p.7 - 9, 1996/00

no abstracts in English

Journal Articles

Current status of HTTR development and heat application test

Saito, Shinzo

Gensan Semina "Koon Gasuro Kaihatsu To Netsu Riyo Gijutsu No Tembo", p.1 - 10, 1992/02

no abstracts in English

Journal Articles

Estimation of 「nuclear energy」 in mid-21st century high temperature gas-cooled reactor

Saito, Shinzo

Genshiryoku Kogyo, 38(1), p.24 - 30, 1992/01

no abstracts in English

Journal Articles

High-Temperature Gas-cooled Reactors (HTGRs) and their potential for non-electric application

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

Journal Articles

High temperature gas-cooled reactor and its utilization

Netsu Enerugi Shohi To Chikyu Kankyo Hogo No Hohoron, p.173 - 187, 1990/05

no abstracts in English

Journal Articles

Chemical application of nuclear reactor heat

Nippon Genshiryoku Gakkai-Shi, 27(5), p.403 - 410, 1985/00

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of multiparpose VHTR

; ;

Nippon Genshiryoku Gakkai-Shi, 25(12), p.971 - 978, 1983/00

 Times Cited Count:1 Percentile:76.9(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Utilization of reactor heat and hydrogen energy

Nippon Genshiryoku Gakkai-Shi, 18(11), p.685 - 690, 1976/11

no abstracts in English

Oral presentation

Features of HTGR and HTGR development in JAEA

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.

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