Study on effect of distribution of neutron flux and relaxation of residual stress on iascc crack growth behaviour for bwr reactor internals

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dc.contributor.authorT. Ogawa
dc.contributor.authorM. Itatani
dc.contributor.authorT. Saito
dc.contributor.authorC. Narazaki
dc.contributor.authorY. Narahara
dc.date.accessioned2018-12-18T14:18:57Z
dc.date.available2018-12-18T14:18:57Z
dc.date.issued2017-08-20
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/35903
dc.publisherIASMiRT
dc.relation.ispartofseries02 - Fracture Mechanics and Structural Integrity
dc.relation.ispartofseries02-15 - Stress Corrosion Cracking Issue
dc.relation.ispartofseries00 - SMiRT 24 - Busan, Republic of Korea. August 20-25, 2017
dc.titleStudy on effect of distribution of neutron flux and relaxation of residual stress on iascc crack growth behaviour for bwr reactor internals
dc.typeConference Proceeding

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2017 - SMiRT 24 - Busan, Republic of Korea