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Journal Articles

Highly thermal conductive sintered SiC fiber-reinforced 3D SiC/SiC composites; Experiments and finite-element analysis of the thermal diffusivity/conductivity

Yamada, Reiji; Igawa, Naoki; Taguchi, Tomitsugu; Jitsukawa, Shiro

Journal of Nuclear Materials, 307-311(Part2), p.1215 - 1220, 2002/12

 Times Cited Count:24 Percentile:80.59(Materials Science, Multidisciplinary)

SiC fiber-reinforced SiC composites (SiC/SiC) are considered an advanced structural material for blanket modules of a fusion reactor, which requires high thermal conductivity in order to keep thermal stresses in the material lower than the allowable design stress. The sintered SiC fiber recently developed has obtained high thermal conductivity, so it is highly expected that sintered SiC fiber-reinforced SiC/SiC composites would also show high thermal conductivity. In this study several types of 3D SiC/SiC composites were fabricated by either CVI or PIP method. The results of the thermal conductivity measurements show that the maximum thermal conductivity at room temperature was about 60 W/mK for CVI composites or 25W/mK for PIP ones. These values are considerably higher than those of non-sintered SiC fiber reinforced SiC/SiC composites, which indicates a possibility that the developed materials would be promising. The FEM thremal analysis shows the good agreement between the caluculated and experimental results.

Journal Articles

Current status of the development of low-activation ferritic steels

Shiba, Kiyoyuki; Hishinuma, Akimichi

Purazuma, Kaku Yugo Gakkai-Shi, 74(5), p.436 - 441, 1998/05

no abstracts in English

Journal Articles

Fabrication technology development of blanket box structure made of reduced activation ferritic steel

Furuya, Kazuyuki; Enoeda, Mikio

Purazuma, Kaku Yugo Gakkai-Shi, 74(5), p.442 - 447, 1998/05

no abstracts in English

JAEA Reports

Development of HIP bonding procedure and mechanical properties of HIP bonded joints for reduced activation ferritic steel F-82H

*; Kurasawa, Toshimasa; Kuroda, Toshimasa*; Hatano, Toshihisa; Takatsu, Hideyuki

JAERI-Tech 97-013, 141 Pages, 1997/03

JAERI-Tech-97-013.pdf:16.98MB

no abstracts in English

JAEA Reports

Feasibility study of first wall electrical connector

*; Takatsu, Hideyuki; Koizumi, Koichi; Tsunematsu, Toshihide

JAERI-Tech 95-032, 17 Pages, 1995/05

JAERI-Tech-95-032.pdf:0.73MB

no abstracts in English

JAEA Reports

Research and Development of Austenitic Stainless Steels for Fusim Reactor

Shiraishi, K.; *; *; *; *; *; *; *; *; *; et al.

JAERI-M 84-189, 220 Pages, 1984/09

JAERI-M-84-189.pdf:14.7MB

no abstracts in English

JAEA Reports

Preliminary Study of Suimming Pool Type Tokamak Reactor

JAERI-M 9050, 81 Pages, 1980/08

JAERI-M-9050.pdf:2.17MB

no abstracts in English

JAEA Reports

Oral presentation

Preliminary design fatigue curves for reduced activation ferritic/martensitic steel, F82H

Hirose, Takanori; Sakasegawa, Hideo; Tanigawa, Hisashi; Tanigawa, Hiroyasu; Kawamura, Yoshinori

no journal, , 

Material database for reduced activation ferritic/martensitic steel, F82H have been accumulated for design study on tritium breeding blanket. This study reports fatigue properties of F82H including effects of test temperature and test atmosphere to establish design fatigue curve. It is found that temperature effects on fatigue lifetime is significant above 450$$^{circ}$$C. As for effects of test atmosphere, lifetime in the vacuum was 5 times higher than that in the air at 550$$^{circ}$$C.

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