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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

Research and development for gas turbine system in GTHTR300

Kunitomi, Kazuhiko; Katanishi, Shoji; Takada, Shoji; Takizuka, Takakazu; Yan, X.; Kosugiyama, Shinichi

JSME International Journal, Series B, 47(2), p.261 - 267, 2004/05

The GTHTR300 aiming at electric generation with its thermal efficiency of 46 % is a safe and economically competitive HTGR in 2010s. A helium gas turbine system connected with the reactor is designed based on existing technologies developed for fossil gas turbine systems. However, there are some uncertainties in performance of a helium gas compressor, electric magnetic bearings and control system. In order to confirm these technical uncertainties, a 1/3 scale model of the compressor and 1/3 scale magnetic bearings will be manufactured and tested in the simulated condition of the GTHTR300. This paper describes R&D plans focusing on the 1/3 scale compressor model test as well as unique design features of the GTHTR300.

Journal Articles

FP plate-out and compound formation analysis in hot helium coolant of 600MWt GTHTR300 system by FP concentration difference diffusion and aerosol-condensation mechanism

Ishiyama, Shintaro

Nippon Genshiryoku Gakkai Wabun Rombunshi, 3(1), p.106 - 119, 2004/03

To estimate FP deposition rate on the typical turbomachinary including gas turbin of GTHTR300 and exposure dose limit at its maintenance, FP plate-out analysis was been carried out using FP compound formation theory and FP concentration controlled diffusion mechanisum. As the results, following conclusions were derived. (1) It is found that the analysis data computed by the VICTORIA code with assumption of the correct thickness of reactive zone exhibits very good correiation with the experimental data obtained by simulated FP plate-out experiment. (2) Total dose rate and allowable work time at turbin of GTHTR300 are given as 19.2mSv/h and 2.6hours by VICTORIA code analysis.

Journal Articles

Maintenance methods and procedures for the power conversion system of the Gas Turbine High Temperature Reactor 300 (GTHTR300)

Kosugiyama, Shinichi; Takei, Masanobu; Takizuka, Takakazu; Takada, Shoji; Yan, X.; Kunitomi, Kazuhiko

Nippon Genshiryoku Gakkai Wabun Rombunshi, 2(4), p.532 - 545, 2003/12

no abstracts in English

Journal Articles

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

Nakata, Tetsuo*; Katanishi, Shoji; Takada, Shoji; Yan, X.; Kunitomi, Kazuhiko

Nippon Genshiryoku Gakkai Wabun Rombunshi, 2(4), p.478 - 489, 2003/12

no abstracts in English

Journal Articles

Basic policy of maintenance for the power conversion system of the Gas Turbine High Temperature Reactor 300 (GTHTR300)

Kosugiyama, Shinichi; Takizuka, Takakazu; Kunitomi, Kazuhiko; Yan, X.; Katanishi, Shoji; Takada, Shoji

Nippon Genshiryoku Gakkai Wabun Rombunshi, 2(3), p.319 - 331, 2003/09

no abstracts in English

Journal Articles

Feasibility study on high burnup fuel for Gas Turbine High Temperature Reactor (GTHTR300),1

Katanishi, Shoji; Kunitomi, Kazuhiko; Takei, Masanobu; Nakata, Tetsuo; Watanabe, Takashi*; Izumiya, Toru*

Nippon Genshiryoku Gakkai Wabun Rombunshi, 1(4), p.373 - 383, 2002/12

no abstracts in English

Journal Articles

Design study on Gas Turbine High Temperature Reactor (GTHTR300) in FY2001

Kunitomi, Kazuhiko; Katanishi, Shoji; Takada, Shoji; Takizuka, Takakazu; Yan, X.; Nakata, Tetsuo; Takei, Masanobu; Kosugiyama, Shinichi; Shiozawa, Shusaku

Nippon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.181 - 184, 2002/00

no abstracts in English

JAEA Reports

Study on the safety system in the High Temperature Gas Cooled Reactor (Contract research)

Nishihara, Tetsuo; Muto, Yasushi; Uchida, Shoji*; Yoshioka, Naoki*

JAERI-Tech 2001-077, 44 Pages, 2001/12

JAERI-Tech-2001-077.pdf:2.16MB

JAERI has conducted the feasibility study of the HTGR gas turbine system from 1996 to 2000 sponsored by MEXT. This report concludes the safety criteria and rationalization of the safety items in the HTGR system.With respect to the safety criteria, the same value for the LWR is selected as the limit of radiation exposure. Probability of the design basis event (DBE) and beyond design basis event (BDBE) is set lower than those for the LWR to get higher safety margin. Adequate initial events and mitigation system are selected to consider the event sequence. The concept of the probability analysis is applied to identify DBEs and BDBEs. It is found that some safety items can be rationalized in consideration of the safety features of the HTGR. Finally, the safety class and design category of the items in the HGTR-GT are classified.

Journal Articles

Development of the compact heat exchanger for the HTGR, 2; Heat transfer and fluid characteristics test

Ishiyama, Shintaro; Muto, Yasushi; Ogata, Hiroshi*; Kamito, Yoshimi*

Nippon Genshiryoku Gakkai-Shi, 43(7), p.708 - 717, 2001/07

 Times Cited Count:2 Percentile:78.99(Nuclear Science & Technology)

no abstracts in English

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

Journal Articles

Conceptual design of a 50-MW severe-accident-free HTR and the related test program of the HTTR

Kunitomi, Kazuhiko; Tachibana, Yukio; Saikusa, Akio; Sawa, Kazuhiro; L.M.Lidsky*

Nuclear Technology, 123(3), p.245 - 258, 1998/09

 Times Cited Count:4 Percentile:59.66(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

General characteristics and technical subjects on helium closed cycle gas turbine

Shimomura, Hiroaki

JAERI-Research 96-034, 73 Pages, 1996/06

JAERI-Research-96-034.pdf:2.47MB

no abstracts in English

Journal Articles

Coking determination in gas turbine engine nozzles using neutron radiography

J.T.Lindsay*; Fujine, Shigenori*; Mishima, Kaichiro*; Hibiki, Takashi*; Yoneda, Kenji*; *; Matsubayashi, Masahito; M.N.Islam*

Fifth World Conf. on Neutron Radiography, 0, p.571 - 577, 1996/00

no abstracts in English

JAEA Reports

A Study of silver behavior in gas-turbine high temperature gas-cooled reactor

Sawa, Kazuhiro; Tanaka, Toshiyuki

JAERI-Research 95-071, 23 Pages, 1995/11

JAERI-Research-95-071.pdf:0.53MB

no abstracts in English

Journal Articles

Development of turbo-viscous pump with ceramic rotor assembly and oil-free driving unit

Murakami, Yoshio; Abe, Tetsuya; *; *

J. Vac. Sci. Technol., A, 9(3), p.2053 - 2057, 1991/05

no abstracts in English

17 (Records 1-17 displayed on this page)
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