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Search Results: Records 1-14 displayed on this page of 14
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Journal Articles

HTGR material

Tsuji, Hirokazu

Nihon Genshiryoku Gakkai-Shi, 41(4), p.383 - 384, 1999/04

no abstracts in English

JAEA Reports

Irradiation embrittlement of 21/4Cr-1Mo steel at 400$$^{circ}$$C

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

JAERI-Research 97-039, 29 Pages, 1997/06

JAERI-Research-97-039.pdf:1.41MB

no abstracts in English

Journal Articles

The HTTR reactor pressure vessel and its integrity against a PTS event

Kurihara, Ryoichi

Nucl. Eng. Des., 172(3), p.317 - 325, 1997/00

https://doi.org/10.1016/S0029-5493(97)00082-4
 Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Post-irradiation fatigue test of 21/4Cr-1Mo steel for the pressure vessel material of the HTTR

; Fukaya, Kiyoshi; Nishiyama, Yutaka; Suzuki, Masahide; Eto, Motokuni; Omi, Masao; Mimura, Hideaki; Ooka, Norikazu

JAERI-Research 96-028, 33 Pages, 1996/06

JAERI-Research-96-028.pdf:1.85MB

no abstracts in English

JAEA Reports

High temperature low cycle fatigue of 21/4Cr-1Mo steel for the HTTR reactor vessel

Nishi, Hiroshi

JAERI-Research 94-031, 14 Pages, 1994/11

JAERI-Research-94-031.pdf:0.92MB

no abstracts in English

Journal Articles

Structural design of pressure vessel of High Temperature Engineering Test Reactor

Kurihara, Ryoichi; Tachibana, Yukio; Nishihara, Tetsuo; Maruyama, So; Shiozawa, Shusaku; *

Atsuryoku Gijutsu, 32(3), p.154 - 165, 1994/00

http://joi.jlc.jst.go.jp/JST.Journalarchive/hpi1972/28.154

no abstracts in English

Journal Articles

The Effect of hold time on low cycle fatigue behavior of 21/4Cr-1Mo steel

S.Chi*; Suzuki, Masahide; Nishi, Hiroshi; Eto, Motokuni; I.Kim*

ISIJ International, 32(4), p.545 - 552, 1992/04

https://doi.org/10.2355/isijinternational.32.545
 Times Cited Count：3 Percentile：42.64(Metallurgy & Metallurgical Engineering)

no abstracts in English

JAEA Reports

Deposition behavior of radio-iodine onto SUS304 stainless steel and 21/4Cr-1Mo steel surfaces

Nakashima, Mikio; Saeki, Masakatsu; Sagawa, Chiaki; ; Hirabayashi, Takakuni; Aratono, Yasuyuki

JAERI-M 91-092, 14 Pages, 1991/06

JAERI-M-91-092.pdf:0.63MB

no abstracts in English

JAEA Reports

Development of methods for generating design allowable limits for the HTTR high-temperature structural design code

Hada, Kazuhiko; Motoki, Yasuo; Baba, Osamu

JAERI-M 90-148, 231 Pages, 1990/09

JAERI-M-90-148.pdf:3.85MB

no abstracts in English

Journal Articles

Current status of reseach and development on high temperature gas cooled reactor and the materials

Kondo, Tatsuo

Nihon Tekko Kyokai Nishiyama Kinen Gijutsu Koza, p.247 - 276, 1990/00

no abstracts in English

Journal Articles

Evaluation of material degradation by thermal aging in 2 1/4Cr-1Mo steels as a structural material for the VHTR

; ; ;

Nihon Gakujutsu Shinkokai Tainetsu Kinzoku Zairyo Dai-123 Iinkai Kenkyu Hokoku, 27(1), p.11 - 20, 1986/00

no abstracts in English

Journal Articles

Stress relaxation of normalized and tempered 2 1/4 Cr-1Mo steel under neutron irradiation

; ; ;

Journal of Nuclear Materials, 132, p.10 - 13, 1985/00

https://doi.org/10.1016/0022-3115(85)90387-3
 Times Cited Count：1 Percentile：24.17(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Temper and neutron irradiation embrittlement in 2 1/4Cr-1 Mo steels for pressure vessels of high-temperature gas-cooled reactors

; ; ;

Nuclear Technology, 66, p.619 - 629, 1984/00

https://doi.org/10.13182/NT84-A33483
 Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Embrittlement of Normaliged and Tempeted 21/4Cr-1Mo Steel by the Temper Embrittlement under Stress

; ; ;

JAERI-M 9150, 30 Pages, 1980/10

JAERI-M-9150.pdf:3.21MB

no abstracts in English

14 (Records 1-14 displayed on this page)
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