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Journal Articles

Probabilistic seismic stability analysis for the ground of quaternary deposits

Hirose, Jiro*; Muramatsu, Ken; Kanda, S.*; Tomishima, S.*; Takeda, Masatoshi*

Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16) (CD-ROM), 8 Pages, 2001/08

no abstracts in English

Journal Articles

Performance tests of reactor containment structures of the HTTR

Iigaki, Kazuhiko; Sakaba, Nariaki; Kawaji, Satoshi; Iyoku, Tatsuo

Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16) (CD-ROM), 7 Pages, 2001/08

no abstracts in English

Journal Articles

Seismic reliability evaluation of electrical power transmission systems and its effect on core damage frequency

Oikawa, Tetsukuni; Fukushima, Seiichiro*; Takase, Hidekazu*; Uchiyama, Tomoaki*; Muramatsu, Ken

Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16) (CD-ROM), 8 Pages, 2001/08

no abstracts in English

Journal Articles

Grain/pore microstructure-based evaluation method for variation of mechanical property of graphite components in the HTGR

Shibata, Taiju; Ishihara, Masahiro

Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16) (CD-ROM), 8 Pages, 2001/08

no abstracts in English

Journal Articles

Applicability of advanced design method of graphite components by microstructure-based brittle fracture model

Ishihara, Masahiro; Takahashi, Tsuneo*; Hanawa, Satoshi

Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16) (CD-ROM), 8 Pages, 2001/08

no abstracts in English

Journal Articles

Fatigue strength reduction factor of partial penetration weldments for ITER vacuum vessel

Nishi, Hiroshi; Eto, Motokuni; Tachibana, Katsumi; Nakahira, Masataka

Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16) (CD-ROM), 8 Pages, 2001/08

Fatigue test of the weldments was performed to investigate their fatigue behavior and the effect of the incomplete penetrations on the fatigue strength. Fatigue crack propagation test of their weld metals was also carried out using CT specimen. By calculating stress intensity factors of the weldments contained the incomplete penetrations and cracks using FEM analysis, the fatigue crack propagation rates of weldments were evaluated and compared those of their weld metals. Fatigue life of the weldments was evaluated based on fracture mechanics to discuss the effect of incomplete penetrations on the fatigue strength. As the results, the incomplete penetration behaved as a crack and most of total fatigue life for the weldment was crack propagation life. The crack propagation rates of weldment were in accordance with those of the weld metals. The fatigue strength of the weldment was considerably lower than that of smoothed specimen. The incomplete penetrations affected greatly the fatigue strength of the weldments even if the depth of incomplete penetrations was small.

Journal Articles

Design method of vertical component isolation system

Kitamura, Seiji; Morishita, Masaki

CD paper #1264, 0 Pages, 2001/00

None

Journal Articles

Feasibility Studies on Commercialized Fast Breeder Reactor System(1)-Sodium Cooled Fast Breeder Reactor

Nibe, Nobuaki; Shimakawa, Yoshio; Kasai, Shigeo;

Final Program and Ab, 0 Pages, 2001/00

None

Journal Articles

Comparison of the CEA and JNC approaches for creep-fatigue evaluation of weldment(2)Benchmark analysis of bending plates

Kasahara, Naoto; Touboul, F.*

Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16), 0 Pages, 2001/00

None

Journal Articles

Feasibility Studies on Commercialized Fast Breeder Reactor System(3)-HLMC Fast Reactor-

; ; Tanaka, Yoshihiko;

Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16), 53 Pages, 2001/00

None

Journal Articles

Feasibility Studies on Commercialized Fast Breeder Reactor System (2)Gas -Cooled High Temperature FBR

; ; Kida, Masanori;

Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16), 534 Pages, 2001/00

None

Journal Articles

Neutron Fluence Database of Experimental Fast Reactor JOYO for Fueland Structural Material Irradiation Tests

; Aoyama, Takafumi

Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16), 0 Pages, 2001/00

None

Journal Articles

Comparison of the CEA and JNC approaches for creep-fatigue evaluation of weldment, 1; Analysis procedures

Kasahara, Naoto

Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16), 0 Pages, 2001/00

None

Journal Articles

Comparison of the CEA and JNC approaches for creep-fatigue evaluation of weldment, 3; Benchmark analysis of a vessel subjected to thermal transients

Kasahara, Naoto

Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16), 0 Pages, 2001/00

None

Journal Articles

A Study of mechanical integrity of coated particle fuel under high burnup irradiation

Sawa, Kazuhiro; Ueta, Shohei; Sumita, Junya; Tobita, Tsutomu*; Minato, Kazuo

Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16) (CD-ROM), 11 Pages, 2001/00

no abstracts in English

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