In the lifetime prediction and extension of a nuclear power plant, a reactor pressure vessel (RPV) has to demonstrate the exclusion of brittle fracture. This paper aims to apply fracture mechanics to analyse the non‐uniform cooling effect in case of a loss‐of‐coolant accident on the RPV integrity. A comprehensive framework coupling reactor system, fluid dynamics, fracture mechanics, and probabilistic analyses for the RPVs integrity analysis is proposed. The safety margin of the allowed RTNDT is increased by more than 16°C if a probabilistic method is applied. Considering the non‐uniform plume cooling effect increases KI more than 30%, increases the failure frequency by more than 1 order of magnitude, and increases the crack tip constraint d...
Development continues on the technology used to assess the safety of irradiation-embrittled nuclear ...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
In the lifetime prediction and extension of a nuclear power plant, a reactor pressure vessel (RPV) h...
In the lifetime prediction and extension of a nuclear power plant, a reactor pressure vessel (RPV) h...
In the lifetime prediction and extension of a nuclear power plant, a reactor pressure vessel (RPV) h...
The Reactor Pressure Vessel (RPV) has long been considered one of the most reliable components in Pr...
AbstractThe failure probabilities of the reactor pressure vessel (RPV) for low temperature over-pres...
The reactor pressure vessel (RPV), the most important component of both pressurized water reactor (P...
At the moment, 11 nuclear power plants (NPP) are under operation in the Russian Federation. More tha...
The relevance of the fracture mechanics in the technology of the nuclear power plant is mainly conn...
The brittle failure assessment for the reactor pressure vessel (RPV) of a 1300 MW pressurized water ...
The failure probabilities of the reactor pressure vessel (RPV) for low temperature over-pressurizati...
In the structural integrity assessment of a pressurized water reactor pressure vessel (RPV) during p...
This paper provides an overview of an improved probabilistic fracture mechanics (PFM) model used for...
Development continues on the technology used to assess the safety of irradiation-embrittled nuclear ...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
In the lifetime prediction and extension of a nuclear power plant, a reactor pressure vessel (RPV) h...
In the lifetime prediction and extension of a nuclear power plant, a reactor pressure vessel (RPV) h...
In the lifetime prediction and extension of a nuclear power plant, a reactor pressure vessel (RPV) h...
The Reactor Pressure Vessel (RPV) has long been considered one of the most reliable components in Pr...
AbstractThe failure probabilities of the reactor pressure vessel (RPV) for low temperature over-pres...
The reactor pressure vessel (RPV), the most important component of both pressurized water reactor (P...
At the moment, 11 nuclear power plants (NPP) are under operation in the Russian Federation. More tha...
The relevance of the fracture mechanics in the technology of the nuclear power plant is mainly conn...
The brittle failure assessment for the reactor pressure vessel (RPV) of a 1300 MW pressurized water ...
The failure probabilities of the reactor pressure vessel (RPV) for low temperature over-pressurizati...
In the structural integrity assessment of a pressurized water reactor pressure vessel (RPV) during p...
This paper provides an overview of an improved probabilistic fracture mechanics (PFM) model used for...
Development continues on the technology used to assess the safety of irradiation-embrittled nuclear ...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...