In order to provide efficient estimates on the safe life of damaged nuclear Reactor Pressure Vessels (RPVs), simulation based models have been created for probabilistic analyses. As probabilistic analyses generally require millions of model evaluations, a model for rapid and accurate stress intensity factor calculations is necessary to obtain useful stochastic results. The Fracture Analysis of Vessels, FAVOR code, is a program designed to perform probabilistic assessments of RPVs, though its analysis is limited to axis aligned flaws for discrete flaw characteristic inputs. In an effort to extend this analysis to 3D off axis flaws for any continuous input, the weight function method utilized in FAVOR was implemented within a finite element f...
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...
This paper provides an overview of an improved probabilistic fracture mechanics (PFM) model used for...
This paper provides an overview of an improved probabilistic fracture mechanics (PFM) model used for...
As a part of the NRC effort to obtain a resolution to the PWR PTS issue, a probabilistic approach ha...
In the lifetime prediction and extension of a nuclear power plant, a reactor pressure vessel (RPV) h...
This thesis begins by noting that the current safety justification of pressurised water reactor pres...
The next generation of fracture assessment procedures for nuclear reactor pressure vessels (RPVs) wi...
This thesis begins by noting that the current safety justification of pressurised water reactor pres...
The pressurized thermal shock( PTS) event poses a potentially significant challenge to the structura...
One of the current tasks within the US Nuclear Regulatory Commission (NRC)-funded Heavy Section Stee...
The Reactor Pressure Vessel (RPV) has long been considered one of the most reliable components in Pr...
ABSTRACT FRACTURE MECHANICS UNCERTAINTY ANALYSIS IN THE RELIABILITY ASSESSMENT OF THE REACTOR PRESS...
The failure probabilities of the reactor pressure vessel (RPV) for low temperature over-pressurizati...
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...
This paper provides an overview of an improved probabilistic fracture mechanics (PFM) model used for...
This paper provides an overview of an improved probabilistic fracture mechanics (PFM) model used for...
As a part of the NRC effort to obtain a resolution to the PWR PTS issue, a probabilistic approach ha...
In the lifetime prediction and extension of a nuclear power plant, a reactor pressure vessel (RPV) h...
This thesis begins by noting that the current safety justification of pressurised water reactor pres...
The next generation of fracture assessment procedures for nuclear reactor pressure vessels (RPVs) wi...
This thesis begins by noting that the current safety justification of pressurised water reactor pres...
The pressurized thermal shock( PTS) event poses a potentially significant challenge to the structura...
One of the current tasks within the US Nuclear Regulatory Commission (NRC)-funded Heavy Section Stee...
The Reactor Pressure Vessel (RPV) has long been considered one of the most reliable components in Pr...
ABSTRACT FRACTURE MECHANICS UNCERTAINTY ANALYSIS IN THE RELIABILITY ASSESSMENT OF THE REACTOR PRESS...
The failure probabilities of the reactor pressure vessel (RPV) for low temperature over-pressurizati...
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...