Irradiation embrittlement rate as well as the re-embrittlement rate after annealing of pressure vessel steels can in general be described by the copper, phosphorus and nickel contents of the materials. In the current study embrittlement and re-embrittlement rate of 32 different model alloys were measured using sub-size CH-V specimens of dimensions 3 × 4 × 27 mm. The impurity and alloy elements of the model alloys were varied within the limits Cu: 0−1.0 wt-%, P = 0−0.040 wt-% and Ni: 0−2.0 wt-% relatively evenly. The specimens were originally irradiated in the high flux reactor in Petten into a neutron fluence of 0.3×1019n/cm2, E >1 MeV and re-irradiated after the annealing treatment in the Loviisa power reactor into a fluence of 1.0 × 10...
A model based on key embrittlement mechanisms is proposed for the analysis. The advantages of such s...
The reactor pressure vessel (RPV) surrounding the core of a commercial nuclear power plant is subjec...
The analysis of WWER-440 RPV welds mechanical properties and behaviour of nanoscale structural featu...
The transition temperature shift recovery efficiency after annealing (475оС, 100 hours) in dependenc...
The dependence of the recovery of the transition temperature shift after annealing (475 °C, 100 h) o...
The dependence of the recovery of the transition temperature shift after annealing (475 °C, 100 h) o...
The radiation embrittlement of the reactor pressure vessel is highly safety-relevant for VVER-type p...
The Reactor Pressure Vessel (RPV) material of Nuclear Power Plants (NPP) is exposed to neutron irrad...
The deep understanding of the irradiation embrittlement of the pressure vessel of nuclear reactors i...
The radiation embrittlement of the reactor pressure vessel is highly safety-relevant for VVER-type p...
The deep understanding of the irradiation embrittlement of the pressure vessel of nuclear reactors i...
In order to assess the validity of post-irradiation annealing as a method to predict results of high...
The radiation embrittlement of the reactor pressure vessel is highly safety-relevant for VVER-type p...
For the prediction of radiation embrittlement of RPV materials beyond the NPP design time the analys...
A model based on key embrittlement mechanisms is proposed for the analysis. The advantages of such s...
A model based on key embrittlement mechanisms is proposed for the analysis. The advantages of such s...
The reactor pressure vessel (RPV) surrounding the core of a commercial nuclear power plant is subjec...
The analysis of WWER-440 RPV welds mechanical properties and behaviour of nanoscale structural featu...
The transition temperature shift recovery efficiency after annealing (475оС, 100 hours) in dependenc...
The dependence of the recovery of the transition temperature shift after annealing (475 °C, 100 h) o...
The dependence of the recovery of the transition temperature shift after annealing (475 °C, 100 h) o...
The radiation embrittlement of the reactor pressure vessel is highly safety-relevant for VVER-type p...
The Reactor Pressure Vessel (RPV) material of Nuclear Power Plants (NPP) is exposed to neutron irrad...
The deep understanding of the irradiation embrittlement of the pressure vessel of nuclear reactors i...
The radiation embrittlement of the reactor pressure vessel is highly safety-relevant for VVER-type p...
The deep understanding of the irradiation embrittlement of the pressure vessel of nuclear reactors i...
In order to assess the validity of post-irradiation annealing as a method to predict results of high...
The radiation embrittlement of the reactor pressure vessel is highly safety-relevant for VVER-type p...
For the prediction of radiation embrittlement of RPV materials beyond the NPP design time the analys...
A model based on key embrittlement mechanisms is proposed for the analysis. The advantages of such s...
A model based on key embrittlement mechanisms is proposed for the analysis. The advantages of such s...
The reactor pressure vessel (RPV) surrounding the core of a commercial nuclear power plant is subjec...
The analysis of WWER-440 RPV welds mechanical properties and behaviour of nanoscale structural featu...