Ten crack-arrest toughness values for irradiated specimens of A 508 class 3 forging steel have been obtained. The tests were performed according to the American Society for Testing and Materials (ASTM) Standard Test Method for Determining Plane-Strain Crack-Arrest Fracture Toughness, K{sub la} of Ferritic Steels, E 1221-88. None of these values are strictly valid in all five ASTM E 1221-88 validity criteria. However, they are useful when compared to unirradiated crack-arrest specimen toughness values since they show the small (averaging approximately 10{degrees}C) shifts in the mean and lower-bound crack-arrest toughness curves. This confirms that a low copper content in ASTM A 508 class 3 forging material can be expected to result in small...
The surveillance test data for the nuclear power plant which is under operation in Ukraine have been...
An integral part of the safety assessment of nuclear pressure vessels and piping is the quantitative...
A capsule containing Charpy V-notch (CVN) and mini-tensile specimens was irradiated at {approximatel...
Indirect measures determined in tests like drop weight NDT have been applied for evaluating the crac...
The objective of this investigation is an estimation of the crack-arrest toughness, particularly of ...
Neutron irradiation-induced embrittlement of the reactor pressure vessel (RPV) leads to an increase ...
Application of the Master Curve method and associated reference temperature of ASTM E1921 to define ...
The exposure of structural materials to the environment in nuclear power plants leads to aging throu...
An extensive mechanical property evaluation has been carried out on various specimens (a Japanese st...
Current regulations require RPV steels to maintain conservative margins of fracture toughness so tha...
The effects of neutron irradiation on the steel reactor vessel for the modular high-temperature gas-...
Recent advances in fracture toughness have led to employment of the Weibull statistic to model scatt...
The steels used for the construction of nuclear reactor pressure vessels are low alloy ferritic stee...
The safety assessment of nuclear pressure vessels and piping requires a quantitative estimation of d...
Ferritic steels usually show significant embrittlement with increasing loading rates in the lower sh...
The surveillance test data for the nuclear power plant which is under operation in Ukraine have been...
An integral part of the safety assessment of nuclear pressure vessels and piping is the quantitative...
A capsule containing Charpy V-notch (CVN) and mini-tensile specimens was irradiated at {approximatel...
Indirect measures determined in tests like drop weight NDT have been applied for evaluating the crac...
The objective of this investigation is an estimation of the crack-arrest toughness, particularly of ...
Neutron irradiation-induced embrittlement of the reactor pressure vessel (RPV) leads to an increase ...
Application of the Master Curve method and associated reference temperature of ASTM E1921 to define ...
The exposure of structural materials to the environment in nuclear power plants leads to aging throu...
An extensive mechanical property evaluation has been carried out on various specimens (a Japanese st...
Current regulations require RPV steels to maintain conservative margins of fracture toughness so tha...
The effects of neutron irradiation on the steel reactor vessel for the modular high-temperature gas-...
Recent advances in fracture toughness have led to employment of the Weibull statistic to model scatt...
The steels used for the construction of nuclear reactor pressure vessels are low alloy ferritic stee...
The safety assessment of nuclear pressure vessels and piping requires a quantitative estimation of d...
Ferritic steels usually show significant embrittlement with increasing loading rates in the lower sh...
The surveillance test data for the nuclear power plant which is under operation in Ukraine have been...
An integral part of the safety assessment of nuclear pressure vessels and piping is the quantitative...
A capsule containing Charpy V-notch (CVN) and mini-tensile specimens was irradiated at {approximatel...