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Hayashi, Koji; Inagaki, Yoshiyuki; Kato, Michio; Fujisaki, Katsuo*; Aita, Hideki; Takeda, Tetsuaki; Nishihara, Tetsuo; Inaba, Yoshitomo; Ohashi, Hirofumi; Katanishi, Shoji; et al.
JAERI-Tech 2005-032, 46 Pages, 2005/06
JAERI-Tech-2005-032.pdf:4.79MB
This is annual report on the experimental operation of the mock-up test facility with a full-scale reaction tube for the HTTR hydrogen production system in 2001 fiscal year. The first experimental operation was performed during two weeks from March 1, 2002 to March 13, 2002 to test on the thermal hydraulic performance of the steam reformer and also to train the operators. The thermal hydraulic performance test of the steam reformer was performed to evaluate the heat transfer characteristics between helium gas and process gas in the steam reformer. This report is summarized with an overview of the test, the results and its operation records.
Sakaki, Akihiro*; Kato, Michio; Hayashi, Koji; Fujisaki, Katsuo*; Aita, Hideki; Ohashi, Hirofumi; Takada, Shoji; Shimizu, Akira; Morisaki, Norihiro; Maeda, Yukimasa; et al.
JAERI-Tech 2005-023, 72 Pages, 2005/04
JAERI-Tech-2005-023.pdf:14.86MB
In order to establish the system integration technology to connect a hydrogen production system to a high temperature gas cooled reactor, the mock-up test facility with a full-scale reaction tube for the steam reforming HTTR hydrogen production system was constructed in fiscal year 2001 and its functional test operation was performed in the year. Seven experimental test operations were performed from fiscal year 2001 to 2004. On a period of each test operation, there happened some troubles. For each trouble, the cause was investigated and the countermeasures and the improvement works were performed to succeed the experiments. The tests were successfully achieved according to plan.This report describes the improvement works on the test facility performed from fiscal year 2001 to 2004.
Shimizu, Akira; Nishihara, Tetsuo; Moriyama, Koichi*
JAERI-Tech 2004-051, 69 Pages, 2004/06
JAERI-Tech-2004-051.pdf:4.68MB
HTTR of JAERI will be connected with a hydrogen production system by steam reforming of methane for development of nuclear heat utilization technology. This facility will handle much inflammable gas near the nuclear reactor so that special safety consideration is necessary. This report describes the Probabilistic Safety Assessment (PSA) of inflammable gas leakage in the HTTR hydrogen production system. Vessels and pipes, which contain flammable gas, were divided into several systems. Probability of gas leakage were calculated at all candidate places. As a result of assessment, the counter measures such as double-covered inflammable gas pipes, small diameter instrument pipes, leakage detector and emergency shut off valves, are confirmed to be very effective to minimize the scale of explosion and to prevent the damage on nuclear plant.
Ohashi, Hirofumi; Inaba, Yoshitomo; Nishihara, Tetsuo; Inagaki, Yoshiyuki; Takeda, Tetsuaki; Hayashi, Koji; Katanishi, Shoji; Takada, Shoji; Ogawa, Masuro; Shiozawa, Shusaku
Journal of Nuclear Science and Technology, 41(3), p.385 - 392, 2004/03
Times Cited Count：17 Percentile：73.1(Nuclear Science & Technology)Prior to construction of a HTTR hydrogen production system, a mock-up test facility was constructed to investigate transient behavior of the hydrogen production system and to establish system controllability. The Mock-up test facility with a full-scale reaction tube is an approximately 1/30 scale model of the HTTR hydrogen production system and an electric heater is used as a heat source instead of a reactor. Before the mock-up test, a performance test of the test facility was carried out in the same pressure and temperature conditions as those of the HTTR hydrogen production system to investigate its performance such as hydrogen production ability, controllability and so on. It was confirmed that hydrogen was stably produced with a hot helium gas about 120Nm
/h which satisfy the design value and thermal disturbance of helium gas during the start-up could be mitigated within the design value by using a steam generator.
Nishihara, Tetsuo; Shimizu, Akira; Inagaki, Yoshiyuki; Tanihira, Masanori*
Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(4), p.517 - 524, 2003/12
no abstracts in English
Ohashi, Hirofumi; Inagaki, Yoshiyuki
JAERI-Tech 2003-046, 47 Pages, 2003/05
JAERI-Tech-2003-046.pdf:3.15MB
no abstracts in English
Inagaki, Yoshiyuki; Hayashi, Koji; Kato, Michio; Fujisaki, Katsuo; Aita, Hideki; Takeda, Tetsuaki; Nishihara, Tetsuo; Inaba, Yoshitomo; Ohashi, Hirofumi; Katanishi, Shoji; et al.
JAERI-Tech 2003-034, 129 Pages, 2003/05
JAERI-Tech-2003-034.pdf:7.62MB
no abstracts in English
Nishihara, Tetsuo; Shimizu, Akira; Tanihira, Masanori*; Uchida, Shoji*
JAERI-Tech 2002-101, 46 Pages, 2003/01
no abstracts in English
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.
Ohashi, Hirofumi; Inagaki, Yoshiyuki; Ogawa, Masuro; Onuki, Kaoru; Takeda, Tetsuaki; Nishihara, Tetsuo; Hayashi, Koji; Inaba, Yoshitomo; Shiozawa, Shusaku
Suiso Enerugi Shisutemu, 26(2), p.23 - 28, 2001/12
no abstracts in English
Nishihara, Tetsuo; Shiozawa, Shusaku; Ogawa, Masuro
IAEA-TECDOC-1236, p.11 - 25, 2001/08
Design and evaluation of heat utilization systems for the high temperature engineering test reactor was carried out as the Coordinated Research Program in the IAEA from 1994 to 1999. The final technical document was published as the TECDOC. The chapter 3, outline of the HTTR, and section 5.2.1, Japanese process design to steam reforming of methane for hydrogen production, were written by JAERI.
Inaba, Yoshitomo; Fumizawa, Motoo*; Tonogochi, Makoto*; Takenaka, Yutaka*
Applied Energy, 67(4), p.395 - 406, 2000/12
Times Cited Count：10 Percentile：50.66(Energy & Fuels)no abstracts in English
Miyamoto, Yoshiaki; Shiozawa, Shusaku; Ogawa, Masuro; Inagaki, Yoshiyuki; Nishihara, Tetsuo; Shimizu, Saburo
Proceedings of International Hydrogen Energy Forum 2000, 2, p.271 - 278, 2000/00
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; Haga, Katsuhiro; ; Sekita, Kenji; *; Hino, Ryutaro
Nihon Genshiryoku Gakkai-Shi, 40(1), p.59 - 64, 1998/00
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)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; ; Sekita, Kenji; Haga, Katsuhiro; Hino, Ryutaro
JAERI-Research 97-076, 33 Pages, 1997/10
JAERI-Research-97-076.pdf:1.3MB
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
Hada, Kazuhiko
JAERI-Research 96-054, 28 Pages, 1996/10
JAERI-Research-96-054.pdf:1.01MB
no abstracts in English
