In the Master Curve (MC) fracture model, a universal temperature dependence is assumed for ferritic steels, including those used in reactor pressure vessel (RPV) applications. The assumed curve shape also has been observed to be generally valid for highly irradiated or thermally aged materials that exhibit a high value of reference transition temperature, To. Lower than predicted fracture toughness behavior occasionally has been observed, however, in the upper transition range. It has been suggested that this behavior possibly may be associated with a lowered upper shelf toughness due to high irradiation doses. One objective of the present International Atomic Energy Agency (IAEA) Coordinated Research Project 8 (CRP-8) is to clarify the MC ...
The paper presents results of a research project founded by the Swiss Federal Nuclear Inspectorate c...
The paper presents results of a research project founded by the Swiss Federal Nuclear Inspectorate c...
Fracture toughness is a key parameter for evaluating the structural integrity of reactor pressure ve...
In the Master Curve (MC) fracture model, a universal temperature dependence is assumed for ferritic ...
The fracture toughness temperature dependence (transition curve shape) has been discussed almost sin...
The fracture toughness temperature dependence (transition curve shape) has been discussed almost sin...
A critical issue in the irradiation damage evaluation of reactor pressure vessel steels is the effec...
A critical issue in the irradiation damage evaluation of reactor pressure vessel steels is the effec...
The precracked Charpy single-edge notched bend, SE(B), specimen (PCC) is the most likely specimen ty...
Recent advances in fracture toughness have led to employment of the Weibull statistic to model scatt...
Ferritic steels usually show significant embrittlement with increasing loading rates in the lower sh...
ABSTRACT For construction of the fracture toughness temperature curve that may be used for WWER RPV ...
Current regulations require RPV steels to maintain conservative margins of fracture toughness so tha...
Neutron irradiation-induced embrittlement of the reactor pressure vessel (RPV) leads to an increase ...
The master curve (MC) approach used to measure the transition temperature, T0, was standarised in th...
The paper presents results of a research project founded by the Swiss Federal Nuclear Inspectorate c...
The paper presents results of a research project founded by the Swiss Federal Nuclear Inspectorate c...
Fracture toughness is a key parameter for evaluating the structural integrity of reactor pressure ve...
In the Master Curve (MC) fracture model, a universal temperature dependence is assumed for ferritic ...
The fracture toughness temperature dependence (transition curve shape) has been discussed almost sin...
The fracture toughness temperature dependence (transition curve shape) has been discussed almost sin...
A critical issue in the irradiation damage evaluation of reactor pressure vessel steels is the effec...
A critical issue in the irradiation damage evaluation of reactor pressure vessel steels is the effec...
The precracked Charpy single-edge notched bend, SE(B), specimen (PCC) is the most likely specimen ty...
Recent advances in fracture toughness have led to employment of the Weibull statistic to model scatt...
Ferritic steels usually show significant embrittlement with increasing loading rates in the lower sh...
ABSTRACT For construction of the fracture toughness temperature curve that may be used for WWER RPV ...
Current regulations require RPV steels to maintain conservative margins of fracture toughness so tha...
Neutron irradiation-induced embrittlement of the reactor pressure vessel (RPV) leads to an increase ...
The master curve (MC) approach used to measure the transition temperature, T0, was standarised in th...
The paper presents results of a research project founded by the Swiss Federal Nuclear Inspectorate c...
The paper presents results of a research project founded by the Swiss Federal Nuclear Inspectorate c...
Fracture toughness is a key parameter for evaluating the structural integrity of reactor pressure ve...