Within the IAEA coordinated programme on optimizing of reactor pressure vessel surveillance programmes and their analysis, phase 3, a specially tailored radiation sensitive correlation monitor material, a Japanese steel plate with code designation JRQ, a French forging material (FFA) and a Japanese forging material (JFL) were selected for the investigations to be carried out in Finland.Based on the evaluation of the experimental results it was demonstrated that dynamic fracture toughness transition shift is equivalent to the Charpy-V shift, but the static fracture toughness transition shift may be considerably larger than the dyanamic shift. Thus, Charpy-V is not suitable for estimating the static fracture toughness transition shift.These f...
International audienceNuclear pressure vessel steels are subjected to irradiation embrittlement whic...
This report discusses development on the technology used to assess the safety of irradiation-embritt...
In the Master Curve (MC) fracture model, a universal temperature dependence is assumed for ferritic ...
An extensive mechanical property evaluation has been carried out on various specimens (a Japanese st...
ABSTRACT Nuclear pressure vessel steels are subjected to irradiation embrittlement which is monitore...
The irradiation response of the extensively evaluated Japanese pressure vessel plate material, JRQ, ...
Within the IAEA Coordinated Research Programme on optimising of reactor pressure vessel surveillance...
The irradiation response of the French forging material FFA offered by International Atomic Energy A...
An extensive evaluation of three different materials in the as-received and irradiated condition has...
The surveillance test data for the nuclear power plant which is under operation in Ukraine have been...
Recent investigations have shown that the Charpy-V test is an unreliable indicator of the true irrad...
Both Charpy-V and precracked Charpy-size specimens were included in the original surveillance progra...
IAEA CRP 3 was a major effort to develop and validate surveillance methodologies for irradiation emb...
A critical issue in the irradiation damage evaluation of reactor pressure vessel steels is the effec...
The mechanical performance of reactor pressure vessel (RPV) materials is an important factor in dete...
International audienceNuclear pressure vessel steels are subjected to irradiation embrittlement whic...
This report discusses development on the technology used to assess the safety of irradiation-embritt...
In the Master Curve (MC) fracture model, a universal temperature dependence is assumed for ferritic ...
An extensive mechanical property evaluation has been carried out on various specimens (a Japanese st...
ABSTRACT Nuclear pressure vessel steels are subjected to irradiation embrittlement which is monitore...
The irradiation response of the extensively evaluated Japanese pressure vessel plate material, JRQ, ...
Within the IAEA Coordinated Research Programme on optimising of reactor pressure vessel surveillance...
The irradiation response of the French forging material FFA offered by International Atomic Energy A...
An extensive evaluation of three different materials in the as-received and irradiated condition has...
The surveillance test data for the nuclear power plant which is under operation in Ukraine have been...
Recent investigations have shown that the Charpy-V test is an unreliable indicator of the true irrad...
Both Charpy-V and precracked Charpy-size specimens were included in the original surveillance progra...
IAEA CRP 3 was a major effort to develop and validate surveillance methodologies for irradiation emb...
A critical issue in the irradiation damage evaluation of reactor pressure vessel steels is the effec...
The mechanical performance of reactor pressure vessel (RPV) materials is an important factor in dete...
International audienceNuclear pressure vessel steels are subjected to irradiation embrittlement whic...
This report discusses development on the technology used to assess the safety of irradiation-embritt...
In the Master Curve (MC) fracture model, a universal temperature dependence is assumed for ferritic ...