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Journal Articles

Correlation between cleavage fracture toughness and charpy impact properties in the transition temperature range of reactor pressure vessel steels

Onizawa, Kunio; Suzuki, Masahide

JSME International Journal, Series A, 47(3), p.479 - 485, 2004/07

In the structural integrity assessment of reactor pressure vessel, fracture toughness values are estimated by assuming that the radiation effect on fracture toughness is equivalent to that on Charpy properties. Therefore, it is necessary to establish the correlation between both properties especially on irradiation embrittlement. In this paper, we present the fracture toughness data obtained by applying the master curve approach that was adopted recently in the ASTM test method. Materials used in this study are five ASTM A533B class 1 steels and one weld metal. Neutron irradiation for Charpy-size specimens as well as standard Charpy-v specimens was carried out at the Japan Materials Testing Reactor. The shifts of the reference temperature on fracture toughness due to neutron irradiation are evaluated. Correlation between the fracture toughness reference temperature and Charpy transition temperature is established. Based on the correlation, the optimum test temperature for fracture toughness testing and the method to determine a lower bound fracture toughness curve are discussed.

Journal Articles

Dynamic effect on fatigue strength of brittle materials

Futakawa, Masatoshi; Kikuchi, Kenji; *;

J. Eur. Ceram. Soc., 17, p.1573 - 1578, 1997/00

 Times Cited Count:4 Percentile:38.15(Materials Science, Ceramics)

no abstracts in English

JAEA Reports

An Explication of design data of the graphite structural design code for core support components of High Temperature Engineering Test Reactor

Ishihara, Masahiro; Iyoku, Tatsuo; *; ; Shiozawa, Shusaku

JAERI-M 91-154, 39 Pages, 1991/10

JAERI-M-91-154.pdf:0.73MB

no abstracts in English

JAEA Reports

An Explication of design data of the graphite structural design code for core components of High Temperature Engineering Test Reactor

Ishihara, Masahiro; Iyoku, Tatsuo; *; ; Shiozawa, Shusaku

JAERI-M 91-153, 51 Pages, 1991/10

JAERI-M-91-153.pdf:1.0MB

no abstracts in English

JAEA Reports

An Inspection standard of graphite for the High Temperature Engineering Test Reactor

Toyota, Junji; Iyoku, Tatsuo; Ishihara, Masahiro; Takikawa, Noboru; Shiozawa, Shusaku

JAERI-M 91-102, 61 Pages, 1991/07

JAERI-M-91-102.pdf:1.49MB

no abstracts in English

JAEA Reports

An Explication of the graphite structural design code of core components for the High Temperature Engineering Test Reactor

Iyoku, Tatsuo; Ishihara, Masahiro; *; Shiozawa, Shusaku

JAERI-M 91-083, 31 Pages, 1991/05

JAERI-M-91-083.pdf:1.04MB

no abstracts in English

JAEA Reports

An Explication of the graphite structural design code of core support components for the High Temperature Engineering Test Reactor

Iyoku, Tatsuo; Ishihara, Masahiro; *; Shiozawa, Shusaku

JAERI-M 91-070, 32 Pages, 1991/05

JAERI-M-91-070.pdf:0.94MB

no abstracts in English

Journal Articles

Few problems Concerning evaluation of degration in Cr-Mo low carbon steel for nuclear structural materials caused by long-term service usage

; ; ;

Nihon Genshiryoku Gakkai-Shi, 27(8), p.722 - 724, 1985/00

 Times Cited Count:0 Percentile:0.33(Nuclear Science & Technology)

no abstracts in English

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