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Journal Articles

Reduced activation martensitic steels as a structural material for ITER test blanket

Shiba, Kiyoyuki; Enoeda, Mikio; Jitsukawa, Shiro

Journal of Nuclear Materials, 329-333(Part1), p.243 - 247, 2004/08

 Times Cited Count:46 Percentile:5.26(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Investigation of the properties of high temperature resistance alloys used in the helium gas cooled high temperature reactor

Uwaba, Tomoyuki

JNC-TN9420 2000-005, 28 Pages, 2000/03

JNC-TN9420-2000-005.pdf:0.94MB

In the first phase of the feasibility study, their basic objectives are presentating the feasible image and scenario of development of the FBR cycle system, which is composed of the fast reactor, spent fuel reprocessing and fuel manufacturing facility. In the development of the FBR system in this phase, various ideas of plants are to be studied, which include coolant types such as sodium, heavy metals, gases(CO$$_{2}$$, He), wator, and middle or small size of the reactor, and fuel types (MOX, metal and nitride). In this report, as a part of this study, materials used for the core of the helium gas cooled reactor and their integrity (corrosion, mechanical and irradiation property) under high temperature helium atmosphere were investigated from open literatures.

Journal Articles

Beryllium neutron irradiation study in the Japan Materials Testing Reactor

; Kawamura, Hiroshi

Fusion Engineering and Design, 41, p.195 - 200, 1998/00

 Times Cited Count:2 Percentile:73.37

no abstracts in English

Journal Articles

Current status and future R&D for reduced-activation ferritic/martensitic steels

Hishinuma, Akimichi; Koyama, Akira*; R.L.Klueh*; D.S.Gelles*; Ehrlich, K.*; W.Dietz*

Journal of Nuclear Materials, 258-263, p.193 - 204, 1998/00

 Times Cited Count:180 Percentile:0.17

no abstracts in English

Journal Articles

Microstructure and mechanical properties of neutron irradiated beryllium

Ishitsuka, Etsuo; Kawamura, Hiroshi; Terai, Takayuki*; Tanaka, Satoru*

Journal of Nuclear Materials, 258-263, p.566 - 570, 1998/00

 Times Cited Count:9 Percentile:36.27

no abstracts in English

Journal Articles

Thermal properties of neutron irradiated beryllium

; Kawamura, Hiroshi; Terai, Takayuki*; Tanaka, Satoru*

Proc. of 5th Int. Workshop on Ceramic Breeder Blanket Interaction, 0, p.215 - 220, 1996/00

no abstracts in English

JAEA Reports

None

Power Reactor and Nuclear Fuel Development Corporation

PNC-TN9360 95-002, 98 Pages, 1995/11

PNC-TN9360-95-002.pdf:4.61MB

no abstracts in English

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