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Journal Articles

Present status of energy in Japan and HTTR project

Ogawa, Masuro; Nishihara, Tetsuo

Nuclear Engineering and Design, 233(1-3), p.5 - 10, 2004/10

 Times Cited Count:27 Percentile:83.6(Nuclear Science & Technology)

An amount of primary energy supply in Japan is increasing year by year. Much energy such as oil, coal and natural gas is imported so that the self-sufficiency ratio in Japan is only 20 % even if including nuclear energy. An amount of energy consumption is also increasing especially in commercial and resident sector and transport sector. As a result, a large amount of greenhouse gas was emitted into the environment. Nuclear energy plays the important role in energy supply in Japan. Japan Atomic Energy Research Institute (JAERI) has been carried out research and development of a hydrogen production system using a high temperature gas cooled reactor (HTGR). The HTTR project aims at the establishment of the HTGR hydrogen production system. Reactor technology of the HTGR, hydrogen production technology with thermochemical water splitting process and system integration technology between the HTGR and a hydrogen production plant are developed in the HTTR project.

Journal Articles

Analytical study on fire and explosion accidents assumed in HTGR hydrogen production system

Inaba, Yoshitomo; Nishihara, Tetsuo; Nitta, Yoshikazu*

Nuclear Technology, 146(1), p.49 - 57, 2004/04

 Times Cited Count:4 Percentile:29.18(Nuclear Science & Technology)

One of the most important safety design issues for a hydrogen production system coupling with a High Temperature Gas-cooled Reactor (HTGR) is to ensure reactor safety against fire and explosion accidents because a large amount of combustible fluid is dealt with in the system. The Japan Atomic Energy Research Institute (JAERI) has a demonstration test plan of a hydrogen production system by steam reforming of methane coupling with the High Temperature engineering Test Reactor (HTTR). In the plan, we developed the P2A code system to analyze event sequences and consequences in detail on the fire and explosion accidents assumed in the HTGR or HTTR hydrogen production system. This paper described the three accident scenarios assumed in the system, the structure of P2A, the analysis procedure with P2A and the results of the numerical analyses based on the accident scenarios, and it was showed that P2A was a useful tool for the accident analysis in the system.

Journal Articles

Performance test results of mock-up test facility of HTTR hydrogen production system

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:72.26(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$$^{3}$$/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.

Journal Articles

Heat transfer characteristics of the steam reformer in the HTTR hydrogen production system

Takeda, Tetsuaki

Proceedings of 12th International Conference on Nuclear Engineering (ICONE-12) (CD-ROM), 4 Pages, 2004/00

no abstracts in English

Journal Articles

Heat transfer characteristics of gas heated type steam reformer

Takeda, Tetsuaki; Ohashi, Hirofumi; Inagaki, Yoshiyuki

Nihon Kikai Gakkai 2003-Nendo Nenji Taikai Koen Rombunshu, Vol.3, p.17 - 18, 2003/08

A technology development of a hydrogen production system by a nuclear heat are being performed as a heat application system of a high-temperature gas cooled reactor in the Japan Atomic Energy Research Institute. The objective of this study is to clarify heat transfer characteristics of the steam reformer in the HTTR hydrogen production system. An experiment has been performed using a double coaxial vertical tube to obtain the heat transfer characteristics and to evaluate the effectiveness of heat transfer enhancement. The amount of produced hydrogen increases with increasing not only reaction rate of catalysis but also the heat transfer coefficient. It is necessary to take into account of heat transfer from both surfaces of the double coaxial tube in order to obtain the amount of transferred heat from the heated tube to the coolant gas.

Journal Articles

Development of control technology for the HTGR hydrogen production system

Nishihara, Tetsuo; Inagaki, Yoshiyuki

Proceedings of GLOBAL2003 Atoms for Prosperity; Updating Eisenhower's Global Vision for Nuclear Energy (CD-ROM), p.320 - 324, 2003/00

HTGR hydrogen production system has potential possibility to provide hydrogen without CO$$_{2}$$ emission. Key technology for developing this system is to establish the control technology for preventing propagation of thermal turbulence from the hydrogen production system to the HTGR. Japan Atomic Energy Research Institute (JAERI) has planed a demonstration test of hydrogen production using an HTGR named high temperature engineering test reactor (HTTR) to develop the control technology. Thermal load absorber concept using the steam generator located downstream of the chemical reactor is proposed to mitigate the variation of outlet helium temperature of the chemical reactor. This concept leads to the stable controllability and enables to operate the HTGR and the hydrogen production plant independently. Plant simulation analyses are carried out to verify the performance of this concept.

JAEA Reports

Development of fire and explosion analysis code system -P2A- for HTGR hydrogen production system (Contract research)

Inaba, Yoshitomo; Nishihara, Tetsuo; Moriyama, Koichi*; Nakamura, Masashi*

JAERI-Data/Code 2002-014, 255 Pages, 2002/07

JAERI-Data-Code-2002-014.pdf:21.69MB

One of the most important safety design issues for an HTGR hydrogen production system is to ensure reactor safety against fire and explosion accidents in the hydrogen production plant because a large amount of combustible fluid is dealt with in the system. JAERI has the demonstration test plan to connect the hydrogen production system with the HTTR. In the plan, we considered effective measures against the fire and explosion accidents in the HTTR hydrogen production system, which were applicable to the HTGR hydrogen production system of a commercial base, and also developed the P2A code system to analyze event sequences and consequences in detail, on assumed fire and explosion accidents in the HTGR hydrogen production system and the HTTR hydrogen production system. The P2A can analyze the process of leakage, dispersion, ignition, and combustion including deflagration and detonation of the combustible fluid in the internal and external area of the reactor building. In this report, we describe the outline and the usage of the P2A, and the results of preliminary calculations.

Journal Articles

Evaluation tritium transportation to the product hydrogen in the HTGR hydrogen production system

Nishihara, Tetsuo; Hada, Kazuhiko

Nihon Genshiryoku Gakkai-Shi, 41(5), p.571 - 578, 1999/05

 Times Cited Count:5 Percentile:40.62(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of methane conversion improvement method by recycling of residual Methane for steam reforming as a part of R&D of HTGR-hydrogen production system

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

JAEA Reports

Proposal of safety design methodologies for an HTGR-hydrogen production system; Mainly on countermeasures against fire and explosion

Nishihara, Tetsuo; Hada, Kazuhiko; Shiozawa, Shusaku

JAERI-Research 97-022, 110 Pages, 1997/03

JAERI-Research-97-022.pdf:4.1MB

no abstracts in English

Journal Articles

Out-of-pile demonstration test program of HTTR hydrogen production system by steam reforming of natural gas

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

Journal Articles

Universally applicable design concept of stably controlling an HTGR-hydrogen production system

Hada, Kazuhiko; Shibata, Taiju; Nishihara, Tetsuo; Shiozawa, Shusaku

Nihon Genshiryoku Gakkai-Shi, 38(10), p.834 - 844, 1996/00

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Utilization of reactor heat and hydrogen energy

Nihon Genshiryoku Gakkai-Shi, 18(11), p.685 - 690, 1976/11

no abstracts in English

13 (Records 1-13 displayed on this page)
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