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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:2 Percentile:16.77(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Structural design of high temperature metallic components

Tachibana, Yukio; Iyoku, Tatsuo

Nuclear Engineering and Design, 233(1-3), p.261 - 272, 2004/10

 Times Cited Count:23 Percentile:79.36(Nuclear Science & Technology)

no abstracts in English

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

Irradiation embrittlement of 2.25Cr-1Mo steel at 400$$^{circ}$$C and its electrochemical evaluation

Nishiyama, Yutaka; Fukaya, Kiyoshi; Suzuki, Masahide; Eto, Motokuni

Journal of Nuclear Materials, 258-263, p.1187 - 1192, 1998/00

 Times Cited Count:4 Percentile:38.34(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Design and fabrication of HTTR reactor pressure vessel

; Tachibana, Yukio; Kunitomi, Kazuhiko;

JAERI-Tech 96-034, 120 Pages, 1996/08

JAERI-Tech-96-034.pdf:3.59MB

no abstracts in English

Journal Articles

Electrochemical evaluation of thermal aging embrittlement of 21/4Cr-1Mo steel for a nuclear pressure vessel

Nishiyama, Yutaka; Fukaya, Kiyoshi; Suzuki, Masahide; Eto, Motokuni;

Small Specimen Test Techniques; ASTM STP 1204, p.16 - 26, 1993/00

no abstracts in English

Journal Articles

Estimation of toughness degradation by microhardness and small punch tests

Suzuki, Masahide; Eto, Motokuni; Nishiyama, Yutaka; Fukaya, Kiyoshi;

Small Specimen Test Techniques; ASTM STP 1204, p.217 - 227, 1993/00

no abstracts in English

Journal Articles

Evaluation of irradiation embrittlement of 21/4Cr-1Mo steel in terms of elastic-plastic fracture toughness

Nishiyama, Yutaka; Fukaya, Kiyoshi; Suzuki, Masahide; Kodaira, Tsuneo; Oku, Tatsuo*

Effects of Radiation on Materials; 15th International Symposium (ASTM STP 1125), p.1287 - 1303, 1992/00

no abstracts in English

Journal Articles

Evaluation of toughness degradation by small punch (SP) tests for neutron-irradiated 21/4Cr-1Mo steel

Suzuki, Masahide; Eto, Motokuni; Fukaya, Kiyoshi; Nishiyama, Yutaka; Kodaira, Tsuneo; Oku, Tatsuo; ; ; ; ; et al.

Journal of Nuclear Materials, 179-181, p.441 - 444, 1991/00

 Times Cited Count:32 Percentile:93.36(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Effect of applied stress on temper embrittlement of 2 1/4 Cr-1Mo steel

; ;

Trans.Iron Steel Inst.Jpn., 22, p.863 - 868, 1982/00

no abstracts in English

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