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Shiozawa, Shusaku; Ogawa, Masuro; Inagaki, Yoshiyuki; Onuki, Kaoru; Takeda, Tetsuaki; Nishihara, Tetsuo; Hayashi, Koji; Kubo, Shinji; Inaba, Yoshitomo; Ohashi, Hirofumi
Proceedings of 17th KAIF/KNS Annual Conference, p.557 - 567, 2002/04
The research and development program on nuclear production of hydrogen was started on January in 1997 as a study consigned by Ministry of Education, Culture, Sports, Science and Technology. A hydrogen production system connected to the HTTR is being designed to be able to produce hydrogen of about 4000 m3/h by steam reforming of natural gas, using a nuclear heat of 10 MW supplied by the HTTR. In order to confirm controllability, safety and performance of key components in the HTTR hydrogen production system, the facility for an out-of-pile test was constructed on the scale of approximately 1/30 of the HTTR hydrogen production system. Essential tests are also carried out to obtain detailed data for safety review and development of analytical codes. Other basic studies on the hydrogen production technology of thermochemical water splitting called an iodine sulfur (IS) process, has been carried out for more effective and various uses of nuclear heat. This paper describes the present status and a future plan on the R&D of the HTTR hydrogen production systems in JAERI.
Huang, Z.*; Ohashi, Hirofumi; Inagaki, Yoshiyuki
JAERI-Tech 2000-022, p.30 - 0, 2000/03
JAERI-Tech-2000-022.pdf:1.24MB
no abstracts in English
Inagaki, Yoshiyuki; Takeda, Tetsuaki; Nishihara, Tetsuo; Hada, Kazuhiko; Hayashi, Koji
Nihon Genshiryoku Gakkai-Shi, 41(3), p.250 - 257, 1999/00
Times Cited Count：10 Percentile：61.08(Nuclear Science & Technology)no abstracts in English
Inagaki, Yoshiyuki; Nishihara, Tetsuo; Takeda, Tetsuaki; Hada, Kazuhiko; Hayashi, Koji
Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00
no abstracts in English
Inagaki, Yoshiyuki; Hada, Kazuhiko; Nishihara, Tetsuo; Takeda, Tetsuaki; Hino, Ryutaro; Haga, Katsuhiro
JAERI-Tech 97-050, 125 Pages, 1997/10
no abstracts in English
Inagaki, Yoshiyuki; Hino, Ryutaro; Hada, Kazuhiko*; Haga, Katsuhiro; Nishihara, Tetsuo; Takeda, Tetsuaki; Shiozawa, Shusaku
Proc. of 5th Int. Conf. on Nucl. Eng. (ICONE-5)(CD-ROM), 5 Pages, 1997/00
no abstracts in English
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JAERI-M 8767, 68 Pages, 1980/03
no abstracts in English
Kimura, Nobuaki; Matsui, Yoshinori; Tobita, Masahiro*; Nakamura, Jinichi; Yamaura, Takayuki
no journal, ,
Power transient tests for the fuels of light water reactors were to be carried out in the Japan Materials Testing Reactor (JMTR) using capsule-type irradiation test facilities, and the integrity of the fuels had been to be investigated by the tests. Prior to the irradiation tests of the fuels, evaluation of thermal-hydraulic behavior in the capsule using ACE-3D code were carried out. And more, the out-pile test facility, which had an electric heater pin instead of a test fuel pin, was designed and fabricated to simulate the capsules used in the power transient tests. Using this facility, necessary tests for the realization of the irradiation tests and the planning of the test methods were carried out. From these analytical and experimental results, it was confirmed that the power ramping tests for 10
10 BWR fuel are able to achieve linear heat rate of 600W/cm in JMTR.
