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JAEA Reports

An Irradiation test of heat-resistant ceramic composite materials, 2; Interim report on post-irradiation examinations of the second and third preliminary test, 98M-41A, 99M-30A

Baba, Shinichi; Nemoto, Makoto*; Sozawa, Shizuo; Yamaji, Masatoshi*; Ishihara, Masahiro; Sawa, Kazuhiro

JAERI-Tech 2005-055, 157 Pages, 2005/09

JAERI-Tech-2005-055.pdf:19.06MB

The Japan Atomic Energy Research Institute (JAERI) has been carrying out the research on radiation damage mechanism of heat-resistant ceramics composite materials, as one of the subjects of the innovative basic research on high temperature engineering using the High Temperature Engineering Test Reactor (HTTR). A series of preliminary irradiation tests is being made using the Japan Materials Testing Reactor (JMTR). The present report describes results of post-irradiation examinations so far on specimens irradiated in the second and third capsule, designated 98M-41A and 99M-30A, to fast neutron fluences of 1.0$$times$$10$$^{25}$$m$$^{-2}$$(E$$>$$1MeV) at temperatures of 973K-1173K and 1273K-1473K. The PIE were conducted as the fundamental statistics index of the diametral dimensions for irradiated specimen, irradiation induced dimensional change rate and thermal expansion rate.

Journal Articles

Lifetime evaluation of graphite components for HTGRs

Oku, Tatsuo*; Ishihara, Masahiro

Nuclear Engineering and Design, 227(2), p.209 - 217, 2004/01

 Times Cited Count:32 Percentile:87.07(Nuclear Science & Technology)

The lifetime of graphite material and/or components has been discussed individually from different concepts, and sometimes gives confusion to material researchers as well as designers. The lifetime of graphite materials is determined based on the dimensional changes due to neutron irradiation, at which they return to their original dimensions after initially contracting. On the other hand, the lifetime of graphite components for HTGRs is defined based on a margin of the specified minimum ultimate strengths of the graphite to the stresses induced in the graphite components. As an example, the stresses induced in the graphite block for the HTTR were, then, compared with the limited stress value determined from the specified minimum ultimate strength, and the lifetime of the graphite component was evaluated and compared with that defined as dimensional changes. As a result, it was found that the lifetime of graphite components for HTGRs should be determined as the shorter one in the two lifetimes defined by the stress-strength relationship and by the dimensional changes.

JAEA Reports

Data on post irradiation experiments of heat resistant ceramic composite materials; PIE for 97M-13A

Baba, Shinichi; Ishihara, Masahiro; Sozawa, Shizuo; Sekino, Hajime

JAERI-Data/Code 2003-003, 394 Pages, 2003/03

JAERI-Data-Code-2003-003.pdf:13.63MB

The research on the radiation damage mechanism of heat resistant ceramic composite materials is one of the research subjects of the innovative basic research in the field of high temperature engineering, using the High Temperature engineering Test Reactor (HTTR). Three series of irradiation tests on the heat resistant ceramic composite materials, first to third irradiation test program, were carried out using the Japan Material Testing Reactor (JMTR). This is a summary report on the the first irradiation test program; irradiation induced dimensional change, thermal expansion coefficient, X-ray diffraction and $$gamma$$-ray spectrum are reported.

Journal Articles

Multi-dimensional thermal-hydraulic analysis for horizontal type PCCS

Arai, Kenji*; Kurita, Tomohisa*; Nakamaru, Mikihide*; Fujiki, Yasunobu*; Nakamura, Hideo; Kondo, Masaya; Obata, Hiroyuki*; Shimada, Rumi*; Yamaguchi, Ken*

Proceedings of 10th International Conference on Nuclear Engineering (ICONE 10) (CD-ROM), 7 Pages, 2002/00

no abstracts in English

Journal Articles

Mechanical properties of neutron-irradiated carbon-carbon composites for plasma facing components

Eto, Motokuni; Ishiyama, Shintaro; ; Fukaya, Kiyoshi;

Journal of Nuclear Materials, 212-215, p.1223 - 1227, 1994/00

 Times Cited Count:18 Percentile:81.22(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Development of thermal/irradiation stress analytical code VIENUS for HTTR graphite block

Iyoku, Tatsuo; Ishihara, Masahiro; *

Journal of Nuclear Science and Technology, 28(10), p.921 - 931, 1991/10

no abstracts in English

JAEA Reports

Analysis of irradiation-induced stresses in coating layers of coated fuel particles for the High Temperature Engineering Test Reactor(HTTR)

Hayashi, Kimio; ; *; Shiozawa, Shusaku; Sawa, Kazuhiro; *; Kikuchi, Teruo; Fukuda, Kosaku

JAERI-M 91-111, 38 Pages, 1991/07

JAERI-M-91-111.pdf:1.41MB

no abstracts in English

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