Improvement of Structural Integrity Assessment Guideline for Fast Reactor Components - Part II: Evaluation of Creep-Fatigue Crack Propagation

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dc.contributor.authorMiura, Naoki
dc.contributor.authorNakayama, Yasunari
dc.contributor.authorTakahashi, Yukio
dc.contributor.authorKishimoto, Kikuo
dc.contributor.authorKitamura, Takayuki
dc.contributor.authorYagawa, Genki
dc.date.accessioned2016-10-10T18:48:45Z
dc.date.available2016-10-10T18:48:45Z
dc.date.issued2001-08-12T00:00:00+00:00
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/30584
dc.publisherIASMiRT
dc.relation.ispartofseriesF - Design Methods and Rules for Components
dc.relation.ispartofseriesF01 -
dc.relation.ispartofseriesSMiRT 16 - Washington, DC, USA. August 12-17, 2001
dc.titleImprovement of Structural Integrity Assessment Guideline for Fast Reactor Components - Part II: Evaluation of Creep-Fatigue Crack Propagation
dc.typeConference Proceeding

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2001 - SMiRT 16 - Washington, DC, USA