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dc.contributor.authorTAYLOR Nigelen_GB
dc.contributor.authorMINNEBO Philipen_GB
dc.contributor.authorBASS Richarden_GB
dc.contributor.authorSIEGELE Dieteren_GB
dc.contributor.authorWALLIN Kimen_GB
dc.contributor.authorKYTKA Milosen_GB
dc.contributor.authorWINTLE Johnen_GB
dc.date.accessioned2010-02-25T14:54:48Z-
dc.date.available2009-01-07en_GB
dc.date.available2010-02-25T14:54:48Z-
dc.date.created2009-01-06en_GB
dc.date.issued2008en_GB
dc.date.submitted2008-10-09en_GB
dc.identifier.citationJOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME vol. 130 no. 3 p. 031407-1 - 031407-11en_GB
dc.identifier.issn0094-9930en_GB
dc.identifier.urihttp://scitation.aip.org/getabs/servlet/GetabsServlet?prog=normal&id=JPVTAS000130000003031407000001&idtype=cvips&gifs=yesen_GB
dc.identifier.urihttp://publications.jrc.ec.europa.eu/repository/handle/JRC48128-
dc.description.abstractIn the NESC-IV project, an experimental/analytical program was performed to develop validated analysis methods for transferring fracture toughness data to shallow flaws in reactor pressure vessels subject to biaxial loading in the lower-transition temperature region. Within this scope, an extensive range of fracture tests was performed on material removed from a production-quality reactor pressure vessel. The master curve analysis of these data is reported and its application to the assessment of the project feature tests on large beam test pieces is discussed.en_GB
dc.description.sponsorshipJRC.F.4-Safety of future nuclear reactorsen_GB
dc.format.mediumPrinteden_GB
dc.languageENGen_GB
dc.publisherASME-AMER SOC MECHANICAL ENGen_GB
dc.relation.ispartofseriesJRC48128en_GB
dc.titleUse of Master Curve Technology for Assessing Shallow Flaws in a Reactor Pressure Vessel Materialen_GB
dc.typeArticles in periodicals and booksen_GB
dc.identifier.doi10.1115/1.2937742en_GB
JRC Directorate:Energy, Transport and Climate

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