The ASME code cases N-629 and N-631 permit the use of a master curve-based index temperature (RTTo≡T0+19.4°C) as an alternative to traditional RTNDT-based methods of positioning the ASME KIC and KIR curves. This approach was adopted to enable the use of master curve technology without requiring the wholesale changes to the structure of the ASME code that would be needed to use all aspects of master curve technology. For the brittle failure analysis considering irradiation embrittlement an additional procedure to predict the adjustment of fracture toughness for end of life (EOL) from irradiation surveillance results must be available as by NRC R.G. 1.99 Rev. 2, e.g., the adjusted reference temperature is defined as ART=initialRTNDT+ΔRTNDT+ma...
The master curve approach for assessing the fracture toughness of a sampled irradiated material has ...
Various aspects of the master curve methodology have been investigated experimentally based on data ...
Neutron irradiation-induced embrittlement of the reactor pressure vessel (RPV) leads to an increase ...
The ASME code cases N-629 and N-631 permit the use of a master curve-based index temperature (RTTo=T...
For the introduction of the new reference temperature RTTo of the ASME Code Cases N-629 and N-631 in...
The fracture toughness temperature dependence (transition curve shape) has been discussed almost sin...
Application of the Master Curve method and associated reference temperature of ASTM E1921 to define ...
The application of the reference temperatures T0 and RTTo according to ASTM E 19 21 and ASME Code Ca...
In the context of existing regulatory codes, the integrity assessment of the pressure vessel of a nu...
AbstractThe master curve methodology proposed by Kim Wallin (ASTM E1921-02) has been used to evaluat...
The conservatism of the RTNDT temperature indexing parameter and the ASME KIR-reference curve with r...
In the Master Curve (MC) fracture model, a universal temperature dependence is assumed for ferritic ...
The paper presents results of a research project founded by the Swiss Federal Nuclear Inspectorate c...
The master curve (MC) approach used to measure the transition temperature, T0, was standarised in th...
Surveillance testing is the basis for all reactor pressure vessel (RPV) integrity and lifetime asses...
The master curve approach for assessing the fracture toughness of a sampled irradiated material has ...
Various aspects of the master curve methodology have been investigated experimentally based on data ...
Neutron irradiation-induced embrittlement of the reactor pressure vessel (RPV) leads to an increase ...
The ASME code cases N-629 and N-631 permit the use of a master curve-based index temperature (RTTo=T...
For the introduction of the new reference temperature RTTo of the ASME Code Cases N-629 and N-631 in...
The fracture toughness temperature dependence (transition curve shape) has been discussed almost sin...
Application of the Master Curve method and associated reference temperature of ASTM E1921 to define ...
The application of the reference temperatures T0 and RTTo according to ASTM E 19 21 and ASME Code Ca...
In the context of existing regulatory codes, the integrity assessment of the pressure vessel of a nu...
AbstractThe master curve methodology proposed by Kim Wallin (ASTM E1921-02) has been used to evaluat...
The conservatism of the RTNDT temperature indexing parameter and the ASME KIR-reference curve with r...
In the Master Curve (MC) fracture model, a universal temperature dependence is assumed for ferritic ...
The paper presents results of a research project founded by the Swiss Federal Nuclear Inspectorate c...
The master curve (MC) approach used to measure the transition temperature, T0, was standarised in th...
Surveillance testing is the basis for all reactor pressure vessel (RPV) integrity and lifetime asses...
The master curve approach for assessing the fracture toughness of a sampled irradiated material has ...
Various aspects of the master curve methodology have been investigated experimentally based on data ...
Neutron irradiation-induced embrittlement of the reactor pressure vessel (RPV) leads to an increase ...