Title: Constraint-Based Master Curve Analysis of a Nuclear Reactor Pressure Vessel Steel
Authors: MINNEBO PhilipCHENEL RAMOS RafaelMENDES JoseDEBARBERIS Luigi
Publisher: Publications Office of the European Union
Publication Year: 2009
JRC N°: JRC55263
ISSN: 1018-5593
Other Identifiers: EUR 24092 EN
URI: http://publications.jrc.ec.europa.eu/repository/handle/JRC55263
Type: EUR - Scientific and Technical Research Reports
Abstract: This report presents the outcome of four fracture test series, addressing the ductile-to-brittle toughness behaviour of a nuclear reactor pressure vessel steel. Each test series corresponds to a specific test specimen geometry, tensile or three-point-bend, with a given degree of crack-tip constraint. A brief overview is given of available constraint-based fracture mechanics methodologies in the ductile-to-brittle transition range, including both engineering and local approach procedures. The obtained experimental data are analysed by means of the Master Curve standard ASTM E1921. Variability of the resulting reference temperature, T0, is successfully confirmed by a selection of constraint-based methodologies.
JRC Institute:Institute for Energy and Transport

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