Creep-Fatigue Crack Propagation In Current International Codes For Components At Elevated Temperatures In Nuclear Engineering: Comparison, Programming And Case Study

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dc.contributor.authorXia QiWei
dc.contributor.authorGong JianGuo
dc.contributor.authorLin Guopeng
dc.contributor.authorXuan Fuzhen
dc.contributor.authorHei BaoPing
dc.contributor.authorGao FuHai
dc.contributor.authorGong Cheng
dc.date.accessioned2020-05-29T20:35:23Z
dc.date.available2020-05-29T20:35:23Z
dc.date.issued2019-08-04
dc.identifier.urihttps://www.lib.ncsu.edu/resolver/1840.20/37856
dc.publisherIASMiRT
dc.relation.ispartofseriesD6 - DESIGN ISSUES, CODES AND STANDARDS
dc.relation.ispartofseriesD6-S3 - Fatigue and Thermal Design
dc.relation.ispartofseries00 - SMiRT 25 - Charlotte, USA. August 4-9, 2019
dc.titleCreep-Fatigue Crack Propagation In Current International Codes For Components At Elevated Temperatures In Nuclear Engineering: Comparison, Programming And Case Study
dc.typeConference Proceeding

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