The authors investigate the influence of chemical and structural inhomogeneity on the brittle fracture resistance (BFR) of VVER vessel materials in the initial state (without irradiation). It is proposed to replace the brittle fracture resistance assessment using the critical brittleness temperature TC for the BFR assessment using the brittle-viscous transition temperature TT. Consideration was given to calibration charts used for studying the TT dependence on the grain size and heat treatment. A comparison of the TC and TT values in the experimental industrial 15H2NMFA-A steel billets shows that the TC values are significantly lower than the TT values: – at the lower level of conservatism, the difference between TC and TT i...
Ferritic steels usually show significant embrittlement with increasing loading rates in the lower sh...
International audienceNeutron irradiation affects the mechanical properties of Reactor Pressure Vess...
A critical issue in the irradiation damage evaluation of reactor pressure vessel steels is the effec...
The efficiency of fracture toughness determined by the methodology of normative document PNAE G-7-00...
Fracture properties of Reactor Pressure Vessel (RPV) steels show large variations with changes in te...
During the course of safety analyses of VVER-plants, the materials and toughness concept for this ty...
Application of the Master Curve method and associated reference temperature of ASTM E1921 to define ...
Failure mechanism of 20MnMoNi55 steel in the lower self of ductile to brittle transition (DBT) regio...
In the Master Curve (MC) fracture model, a universal temperature dependence is assumed for ferritic ...
Fracture toughness is a key parameter for evaluating the structural integrity of reactor pressure ve...
The ductile-to-brittle transition temperatures were calculated from the impact energies measured on ...
In a PWR nuclear power plant, the reactor pressure vessel (RPV) contains the fuel assemblies and rea...
ABSTRACT Nuclear pressure vessel steels are subjected to irradiation embrittlement which is monitore...
The master curve (MC) approach used to measure the transition temperature, T0, was standarised in th...
A series of model alloys are studied to understand irradiation embrittlement phenomena and similitud...
Ferritic steels usually show significant embrittlement with increasing loading rates in the lower sh...
International audienceNeutron irradiation affects the mechanical properties of Reactor Pressure Vess...
A critical issue in the irradiation damage evaluation of reactor pressure vessel steels is the effec...
The efficiency of fracture toughness determined by the methodology of normative document PNAE G-7-00...
Fracture properties of Reactor Pressure Vessel (RPV) steels show large variations with changes in te...
During the course of safety analyses of VVER-plants, the materials and toughness concept for this ty...
Application of the Master Curve method and associated reference temperature of ASTM E1921 to define ...
Failure mechanism of 20MnMoNi55 steel in the lower self of ductile to brittle transition (DBT) regio...
In the Master Curve (MC) fracture model, a universal temperature dependence is assumed for ferritic ...
Fracture toughness is a key parameter for evaluating the structural integrity of reactor pressure ve...
The ductile-to-brittle transition temperatures were calculated from the impact energies measured on ...
In a PWR nuclear power plant, the reactor pressure vessel (RPV) contains the fuel assemblies and rea...
ABSTRACT Nuclear pressure vessel steels are subjected to irradiation embrittlement which is monitore...
The master curve (MC) approach used to measure the transition temperature, T0, was standarised in th...
A series of model alloys are studied to understand irradiation embrittlement phenomena and similitud...
Ferritic steels usually show significant embrittlement with increasing loading rates in the lower sh...
International audienceNeutron irradiation affects the mechanical properties of Reactor Pressure Vess...
A critical issue in the irradiation damage evaluation of reactor pressure vessel steels is the effec...