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Department of HTTR
JAEA-Review 2023-016, 82 Pages, 2023/09
JAEA-Review-2023-016.pdf:2.31MB
The High Temperature Engineering Test Reactor (HTTR) is the first Japanese High Temperature Gas-cooled Reactor (HTGR) with 30MW in thermal power and 950
C of maximum outlet coolant temperature that is constructed by the Japan Atomic Energy Agency located at Oarai-machi, Higashiibaraki-gun, Ibaraki-ken, Japan. The purpose of the HTTR is establishment of basic HTGR technologies, demonstration of HTGR safety characteristics and so on. The HTTR has had a lot of experience of HTGRs' operation and maintenance throughout rated power operations, safety demonstration tests, long-term high temperature operations and demonstration tests relevant to HTGRs' R&Ds. In the fiscal year 2021, as the HTTR completed activities to conform to the New Regulatory Requirements of Nuclear Regulation Authority, The HTTR restarted since the 2011 off the Pacific coast of Tohoku Earthquake and carried out the Loss-of-forced cooling test without Vessel Cooling System (VCS) operational at 9MW (Three gas circulators trip and VCS is stopped.) as the safety demonstration test. This report summarizes the activities carried out in the fiscal year 2021, which were the situation of the New Regulatory Requirements screening of the HTTR, the operation and maintenance of the HTTR, R&Ds relevant to commercial-scale HTGRs, the international cooperation on HTGRs and so on.
Department of HTTR
JAEA-Review 2019-049, 97 Pages, 2020/03
JAEA-Review-2019-049.pdf:4.66MB
The High Temperature Engineering Test Reactor (HTTR), a graphite-moderated and helium gas-cooled reactor being able to get 950C temperature of the outlet coolant with 30 MW of thermal power, constructed at the Oarai Research and Development Institute of the Japan Atomic Energy Agency is the first High- Temperature Gas-cooled Reactor (HTGR) in Japan. The purpose of the HTTR is to establish and upgrade basic technologies for HTGRs. The HTTR has accumulated a lot of experience of HTGRs' operation and maintenance up to the present time throughout rated power operations, safety demonstration tests, long-term high temperature operations and demonstration tests relevant to HTGRs' R&Ds. In the fiscal year 2018, we made effort to pass the inspection of application document for the HTTR licensing to prove conformity with the new regulatory requirements for research reactors that took effect since December 2013 in order to restart operations of the HTTR that stopped since the 2011 off the Pacific coast of Tohoku Earthquake. This report summarizes the activities carried out in the 2018 fiscal year, which were the situation of the new regulatory requirements screening of the HTTR, the operation and maintenance of the HTTR, R&Ds relevant to commercial-scale HTGRs, the international cooperation on HTGRs and so on.
Shimazaki, Yosuke; Yamazaki, Kazunori; Iigaki, Kazuhiko
Hozengaku, 18(1), p.16 - 20, 2019/04
no abstracts in English
Hamamoto, Shimpei; Takada, Shoji
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 4 Pages, 2017/04
Choi, B.; Nishida, Akemi; Nakajima, Norihiro
Proceedings of 24th International Conference on Nuclear Engineering (ICONE-24) (DVD-ROM), 7 Pages, 2016/06
Research and development of three-dimensional vibration simulation technologies for nuclear facilities have been promoted in the Center for Computational Science and e-Systems of the Japan Atomic Energy Agency (JAEA). A seismic intensity of upper 5 was observed in the area of High-Temperature Engineering Test Reactor (HTTR) at the Oarai Research and Development Center of the JAEA during the 2011 Tohoku earthquake. In this paper, we report a parametric study of seismic response analyses of this earthquake using three-dimensional finite element models of the HTTR building with various uncertainty parameters (e.g. soil-structure interaction effects, soil properties). By examining the variation of the response result against the uncertainty parameters, we obtained a knowledge, which is essential for constructing a valid three-dimensional finite element model.
Shimazaki, Yosuke; Ono, Masato; Tochio, Daisuke; Takada, Shoji; Sawahata, Hiroaki; Kawamoto, Taiki; Hamamoto, Shimpei; Shinohara, Masanori
Proceedings of International Topical Meeting on Research Reactor Fuel Management and Meeting of the International Group on Reactor Research (RRFM/IGORR 2016) (Internet), p.1034 - 1042, 2016/03
In High Temperature Engineering Test Reactor (HTTR), three neutron holders containing 
Cf with 3.7 GBq for each are loaded in the graphite blocks and inserted into the reactor core as a neutron startup source which is changed at the interval of approximately ten years. These neutron holders containing the neutron sources are transported from the dealer's hot cell to HTTR using the transportation container. The holders loading to the graphite block are carried out in the fuel handling machine maintenance pit of HTTR. There were two technical issues for the safety handling work of the neutron holder. The one is the radiation exposure caused by significant movement of the container due to an earthquake, because the conventional transportation container was so large (
1240 mm, h1855 mm) that it can not be fixed on the top floor of maintenance pit by bolts. The other is the falling of the neutron holder caused by the difficult remote handling work, because the neutron holder capsule was also so long (155 mm, h1285 mm) that it can not be pulled into the adequate working space in the maintenance pit. Therefore, a new and low cost transportation container, which can solve the issues, was developed. To avoid the neutron and 
ray exposure, smaller transportation container (820mm, h1150 mm) which can be fixed on the top floor of maintenance pit by bolts was developed. In addition, to avoid the falling of the neutron holder, smaller neutron holder capsule (75 mm, h135 mm) with simple handling mechanism which can be treated easily by manipulator was also developed. As the result of development, the neutron holder handling work was safely accomplished. Moreover, a cost reduction for manufacturing was also achieved by simplifying the mechanism of neutron holder capsule and downsizing.
Department of HTTR
JAEA-Review 2014-041, 140 Pages, 2014/12
JAEA-Review-2014-041.pdf:14.06MB
The High Temperature Engineering Test Reactor (HTTR) constructed at the Oarai Research and Development Center of the Japan Atomic Energy Agency (JAEA) is the first high-temperature gas-cooled reactor (HTGR) in Japan which is a graphite-moderated and helium gas-cooled reactor with 30MW of thermal power. In fiscal year 2013, we started to prepare the reactor installation application for the HTTR to prove conformity with the new research reactor's safety regulatory requirements taken effect from December 2013. We had been making effort to run the HTTR which was stopped since the 2011 in which the Pacific coast of Tohoku Earthquake (2011.3.11) occurred. This report summarizes activities and results of HTTR operation, maintenance, and several R&Ds, which were carried out in the fiscal year 2013.
Baba, Shinichi; Ishihara, Masahiro; Suzuki, Yoshio*; Takahashi, Tsuneo*; Hoshiya, Taiji
JAERI-Data/Code 2002-008, 126 Pages, 2002/03
JAERI-Data-Code-2002-008.pdf:4.82MB
no abstracts in English
Kizaki, Minoru; Honda, Junichi; Usami, Koji; Ouchi, Asao*; Oeda, Etsuro; Matsumoto, Seiichiro
JAERI-Tech 2000-087, 50 Pages, 2001/02
JAERI-Tech-2000-087.pdf:2.78MB
no abstracts in English
Research Evaluation Committee
JAERI-Review 2000-020, 28 Pages, 2000/09
JAERI-Review-2000-020.pdf:2.43MB
no abstracts in English
Ogawa, Masuro; Shiina, Yasuaki; Fumizawa, Motoo; Takeda, Tetsuaki; Takada, Shoji; Kubo, Shinji; Inaba, Yoshitomo
JAERI-Tech 98-062, 126 Pages, 1999/01
no abstracts in English
Shigemoto, Masamitsu; Shiozawa, Shusaku
Genshiryoku Nenkan '97, p.129 - 134, 1997/00
no abstracts in English
Kurihara, Ryoichi; Tachibana, Yukio; Nishihara, Tetsuo; Maruyama, So; Shiozawa, Shusaku; *
Atsuryoku Gijutsu, 32(3), p.154 - 165, 1994/00
no abstracts in English
Hino, Ryutaro; *;
Nihon Genshiryoku Gakkai-Shi, 33(7), p.685 - 694, 1991/07
no abstracts in English
Ara, Katsuyuki; ; ; *; *
FAPIG, 0(125), p.19 - 27, 1990/07
no abstracts in English
Saeki, Masakatsu; Nakashima, Mikio; Sagawa, Chiaki; ; Hirabayashi, Takakuni; Aratono, Yasuyuki
JAERI-M 90-084, 14 Pages, 1990/06
no abstracts in English
Shiina, Yasuaki; Kunitomi, Kazuhiko; Maruyama, So; ; Nakagawa, Shigeaki; Hirano, Masashi; Iyoku, Tatsuo; Shindo, Masami; Sudo, Yukio
JAERI-M 90-034, 104 Pages, 1990/03
no abstracts in English
Matsuo, Hideto; Saito, Tamotsu; Imai, Hisashi
JAERI-M 89-080, 18 Pages, 1989/06
no abstracts in English
Kunitomi, Kazuhiko; Suzuki, Kunihiro; Inagaki, Yoshiyuki; Ioka, Ikuo;
Nihon Genshiryoku Gakkai-Shi, 30(7), p.617 - 623, 1988/07
Times Cited Count：1 Percentile：19.68(Nuclear Science & Technology)no abstracts in English
Inagaki, Yoshiyuki
no journal, ,
This presentation describes the current status of the research and development of High Temperature Gas-cooled Reactor (HTGR) and hydrogen production technologies. As for the HTGR technology, futures such as inherent safety and research results with HTTR such as safety demonstration tests are described. As for the hydrogen production technology by thermochemical Iodine-Sulfur (IS) process, the progress situation of the continuous hydrogen production test with test facility made of industrial materials and the demonstration test plan with HTTR and heat utilization facilities are presented.
