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Journal Articles

Reactor pressure vessel design of the high temperature engineering test reactor

Tachibana, Yukio; Nakagawa, Shigeaki; Iyoku, Tatsuo

Nuclear Engineering and Design, 233(1-3), p.103 - 112, 2004/10

 Times Cited Count:1 Percentile:10.51(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Reactor internals design

Sumita, Junya; Ishihara, Masahiro; Nakagawa, Shigeaki; Kikuchi, Takayuki; Iyoku, Tatsuo

Nuclear Engineering and Design, 233(1-3), p.81 - 88, 2004/10

 Times Cited Count:4 Percentile:30.82(Nuclear Science & Technology)

A High Temperature Gas-cooled Reactor is particularly attractive due to its capability of producing high temperature helium gas and its possibility to exploit inherent safety characteristic. To achieve high temperature helium-gas, reactor internals are made of graphite and heat resistant materials, its surroundings are composed of metals. The reactor internals of the HTTR consist of graphite and metallic core support structures and shielding blocks. This paper describes the reactor internal design of the HTTR, especially the core support graphite structures, and the program of an in-service inspection.

Journal Articles

Design and fabrication of reactor pressure vessel for High Temperature Engineering Test Reactor (HTTR)

Tachibana, Yukio; Nakagawa, Shigeaki; Iyoku, Tatsuo

Elevated Temperature Design and Analysis, Nonlinear Analysis, and Plastic Components, 2004 (PVP-Vol.472), p.39 - 44, 2004/07

The reactor pressure vessel (RPV) of the HTTR is 5.5m in inside diameter, 13.2m in inside height, and 122mm and 160mm in wall thickness of the body and the top head dome, respectively. Because the reactor inlet temperature of the HTTR is higher than that of LWRs, 2 1/4Cr-1Mo steel is chosen for the RPV material. Fluence of the RPV is estimated to be less than 1$$times$$10$$^{17}$$n/cm$$^{2}$$(E$$>$$1 MeV), and so irradiation embrittlement is presumed to be negligible, but temper embrittlement is not. For the purpose of reducing embrittlement, content of some elements is limited on 2 1/4 Cr-1 Mo steel for the RPV using embrittlement parameters, J-factor and X-bar. In this paper design, fabrication procedure, and in-service inspection technique of the RPV for the HTTR are described.

Journal Articles

Nondestructive evaluation method on mechanical property change of graphite components in the HTGR by ultrasonic wave propagation with grain/pore microstructure

Shibata, Taiju; Ishihara, Masahiro

Transactions of 17th International Conference on Structural Mechanics in Reactor Technology (SMiRT-17) (CD-ROM), 8 Pages, 2003/08

no abstracts in English

JAEA Reports

Development of in-service inspection system for core support graphite structures in the High Temperature Engineering Test Reactor (HTTR)

Sumita, Junya; Hanawa, Satoshi; Kikuchi, Takayuki; Ishihara, Masahiro

JAERI-Tech 2003-023, 37 Pages, 2003/03

JAERI-Tech-2003-023.pdf:7.79MB

Visual inspection of core support graphite structures using TV camera as in-service inspection and measurement of material characteristics using surveillance test specimens are planned in the High Temperature Engineering Test Reactor (HTTR) to confirm structural integrity of the core support graphite structures. For the visual inspection, in-service inspection system has been developed, and pre-service inspection using the system was carried out. As the result of the pre-service inspection, it was validated that high quality of visual inspection with TV camera can be carried out, and also structural integrity of the core support graphite structures at the initial stage of the HTTR operation was confirmed.

Journal Articles

Grain/pore microstructure-based evaluation method for variation of mechanical property of graphite components in the HTGR

Shibata, Taiju; Ishihara, Masahiro

Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16) (CD-ROM), 8 Pages, 2001/08

no abstracts in English

Journal Articles

Ultrasonic signal characterstics by pulse-echo technique and mechanical strength of graphite materials with porous structure

Shibata, Taiju; Ishihara, Masahiro

Nuclear Engineering and Design, 203(2-3), p.131 - 141, 2001/01

no abstracts in English

Journal Articles

Introduction to reactor safety

Genshiryoku Kogyo, 19(9), p.57 - 62, 1973/09

no abstracts in English

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