Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Takeda, Tetsuaki*; Inagaki, Yoshiyuki; Aihara, Jun; Aoki, Takeshi; Fujiwara, Yusuke; Fukaya, Yuji; Goto, Minoru; Ho, H. Q.; Iigaki, Kazuhiko; Imai, Yoshiyuki; et al.
High Temperature Gas-Cooled Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.5, 464 Pages, 2021/02
As a general overview of the research and development of a High Temperature Gas-cooled Reactor (HTGR) in JAEA, this book describes the achievements by the High Temperature Engineering Test Reactor (HTTR) on the designs, key component technologies such as fuel, reactor internals, high temperature components, etc., and operational experience such as rise-to-power tests, high temperature operation at 950
C, safety demonstration tests, etc. In addition, based on the knowledge of the HTTR, the development of designs and component technologies such as high performance fuel, helium gas turbine and hydrogen production by IS process for commercial HTGRs are described. These results are very useful for the future development of HTGRs. This book is published as one of a series of technical books on fossil fuel and nuclear energy systems by the Power Energy Systems Division of the Japan Society of Mechanical Engineers.
Takada, Shoji; Sekita, Kenji; Nemoto, Takahiro; Honda, Yuki; Tochio, Daisuke; Inaba, Yoshitomo; Sato, Hiroyuki; Nakagawa, Shigeaki; Sawa, Kazuhiro
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 7 Pages, 2015/05
To investigate the safety design criteria of heat utilization system for the HTGRs, it is necessary to evaluate the effect of fluctuation of thermal load on the reactor. The nuclear heat supply fluctuation test by non-nuclear heating was carried out to simulate the nuclear heat supply test which is carried out in the nuclear powered operation. The test data is used to verify the numerical code to calculate the temperature of core bottom structure to carry out the safety evaluation of abnormal events in the heat utilization system. In the test, the helium gas temperature was heated up to 120C. A sufficiently high temperature disturbance was imposed on the reactor inlet temperature. It was found that the response of temperatures of metallic components such as side shielding blocks was faster than those of graphite blocks in the core bottom structure, which was significantly affected by the heat capacities of components, the level of imposed disturbance and heat transfer performance.
Shibanuma, Kiyoshi
Nihon Genshiryoku Gakkai-Shi, 47(11), p.761 - 767, 2005/11
In-vessel components such as blanket and divertor of the fusion reactor are activated by neutron produced during fusion reaction. Gamma radiation will be about 500 MGy/h in maximum after fusion reaction. When the components are failed or troubled in the vessel, the maintenence has to be carried out by the robot because the human cannot be close inside the vessel. The required functions and present R&D status of the typical robots applied to ITER are introduced as examples of robots maintaining the in-vessel components of the fusion reactor.
Toda, Saburo*; Yuki, Kazuhisa*; Akimoto, Hajime
JAERI-Tech 2004-008, 58 Pages, 2004/03
JAERI-Tech-2004-008.pdf:5.14MB
no abstracts in English
Suzuki, Satoshi; Ueda, Yoshio*; Tokunaga, Kazutoshi*; Sato, Kazuyoshi; Akiba, Masato
Fusion Science and Technology, 44(1), p.41 - 48, 2003/07
Times Cited Count：31 Percentile：85.60(Nuclear Science & Technology)no abstracts in English
Shibata, Katsuyuki; Onizawa, Kunio; Li, Y.*; Kato, Daisuke*
Proceedings of 4th International Workshop on the Integrity of Nuclear Components, p.31 - 41, 2002/00
no abstracts in English
Ishihara, Masahiro; Hanawa, Satoshi; Iyoku, Tatsuo; Shiozawa, Shusaku
Tanso, 2001(196), p.39 - 48, 2001/02
no abstracts in English
Kaminaga, Masanori; Murayama, Yoji; ;
JAERI-Tech 97-043, 63 Pages, 1997/09
no abstracts in English
Shibata, Katsuyuki
Nucl. Eng. Des., 174(1), p.79 - 90, 1997/00
Times Cited Count：1 Percentile：14.24(Nuclear Science & Technology)no abstracts in English
Akiba, Masato
Proceedings of Japan-U.S. Workshop on Fusion High Power Density Devices and Design, 2, p.86 - 96, 1997/00
no abstracts in English
; Kakudate, Satoshi; Oka, Kiyoshi; Nakahira, Masataka; ; Obara, Kenjiro; Tada, Eisuke; Shibanuma, Kiyoshi; Seki, Masahiro
JAERI-Tech 94-012, 17 Pages, 1994/08
no abstracts in English
H.-W.Bartels*; Kunugi, Tomoaki; A.J.Russo*
Atomic and Plasma-Material Interaction Data for Fusion, Vol. 5, 0, p.225 - 244, 1994/00
no abstracts in English
; ; Seki, Yasushi
Purazuma, Kaku Yugo Gakkai-Shi, 68(5), p.511 - 515, 1992/11
no abstracts in English
Tada, Eisuke; Yoshida, Kiyoshi; Shibanuma, Kiyoshi; Akiba, Masato; Okumura, Yoshikazu
Kaku Yugo Kenkyu, 68(3), p.249 - 267, 1992/09
no abstracts in English
Ishihara, Masahiro; Iyoku, Tatsuo; ; ; Shiozawa, Shusaku
JAERI-M 91-154, 39 Pages, 1991/10
no abstracts in English
Ishihara, Masahiro; Iyoku, Tatsuo; ; ; Shiozawa, Shusaku
JAERI-M 91-153, 51 Pages, 1991/10
no abstracts in English
Toyota, Junji; Iyoku, Tatsuo; Ishihara, Masahiro; Takikawa, Noboru; Shiozawa, Shusaku
JAERI-M 91-102, 61 Pages, 1991/07
no abstracts in English
Iyoku, Tatsuo; Ishihara, Masahiro; ; Shiozawa, Shusaku
JAERI-M 91-083, 31 Pages, 1991/05
no abstracts in English
Iyoku, Tatsuo; Ishihara, Masahiro; ; Shiozawa, Shusaku
JAERI-M 91-070, 32 Pages, 1991/05
no abstracts in English
; ; ; ; ; ; ;
Nihon Genshiryoku Gakkai-Shi, 30(5), p.427 - 433, 1988/05
Times Cited Count：1 Percentile：19.49(Nuclear Science & Technology)no abstracts in English
