High temperature gas-cooled reactors

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

https://doi.org/10.1016/C2018-0-05383-9

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 950C, 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.

Study on introduction scenario of the high temperature gas-cooled reactor hydrogen cogeneration system (GTHTR300C), 1

Nishihara, Tetsuo; Takeda, Tetsuaki

JAERI-Tech 2005-049, 19 Pages, 2005/09

JAERI-Tech-2005-049.pdf:1.17MB

Japan Atomic Energy Research Institute is carrying out the research and development of the high temperature gas-cooled reactor hydrogen cogeneration system (GTHTR300C) aiming at the practical use around 2030. Preconditions of GTHTR300C introduction are the increase of hydrogen demand and the needs of new nuclear power plants. In order to establish the introduction scenario, it should be clarified that the operational status of existing nuclear power plants, the introduction number of fuel cell vehicles as a main user of hydrogen and the capability of hydrogen supply by existing plants. In this report, the estimation of the nuclear power plants that will be decommissioned with a high possibility by 2030 and the selection of the model district where the GTHTR300C can be introduced as an alternative system are conducted. Then the hydrogen demand and the capability of hydrogen supply in this district are investigated and the hydrogen supply scenario in 2030 is considered.

The Design of the neutron total scattering spectrometer for hydrogenous materials at J-PARC-JSNS

Suzuya, Kentaro; Kameda, Yasuo*; Otomo, Toshiya*; Yoshida, Koji*; Ito, Keiji*; Fukunaga, Toshiharu*; Misawa, Masakatsu*

Journal of Neutron Research, 13(1-3), p.123 - 128, 2005/03

https://doi.org/10.1080/10238160412331299898

The design, performance, philosophy, lessons learned and advantages of the neutron total scattering spectrometer for hydrogenous materials, FAST, under consideration for the J-PARC-JSNS, are described. In particular, novel instrumentation concept such as the small fractional scattered neutron flight path, = L/(L+L), where L is the incident flight path, moderator to sample, L is the scattered neutron flight path from sample to detector, is presented and their expected performance at the JSNS is considered.

High-Temperature Gas-cooled Reactors (HTGRs) and their potential for non-electric application

Saito, Shinzo

Proc. of IEA Int. Conf. on Technology Responses to Global Environmental Challenges,Vol. l, p.393 - 396, 1991/00

no abstracts in English

Post-facta analysis of the TMI accident, I; Analysis of thermal hydraulic behavior by use of the RELAP4/MOD6/U4/J2

; ; ; Shimooke, Takanori

Nucl.Eng.Des., 69(1), p.3 - 36, 1982/00

https://doi.org/10.1016/0029-5493(82)90277-1

no abstracts in English

Reaction calculation of liquid-depth effect on radiolytic hydrogen generation by using a one-dimensional model

Thwe Thwe, A.; Nagaishi, Ryuji; Furukawahara, Ryo; Ito, Tatsuya

no journal, , 

For hydrogen safety in the storage of wet radioactive materials under the decommissioning process of nuclear power stations including 1F, not only the experimental but also analytical studies on hydrogen generation from water radiolysis are important. Until now, we have conducted those closely related to the 1F decommissioning by the experiments for the effects of seawater salts, liquid depth and temperature, and by the calculations for the effect of liquid flow. In this study, we calculated the liquid-depth effect on hydrogen generation by using a one-dimensional reaction model in the vertical direction based on the open-source software CANTERA. The division of reaction cells was found to be important. As the division number increased, the slope of the increase in the amount of hydrogen generated with respect to the absorbed dose became smaller, approaching to the experimental results. However, when the number exceeded 100, the calculation results were underestimated under the current experimental and calculation conditions.