This paper describes the comparative study of two approaches to estimate pipe leak and rupture frequencies for piping. One method is based on a probabilistic fracture mechanistic model while the other one is based on statistical estimation of rupture frequencies from a large database. In order to be able to compare the approaches and their results, the rupture frequencies of some selected welds have been estimated using both of these methods. This paper highlights the differences both in methods, input data, need and use of plant specific information and need of expert judgement. The study focuses on one specific degradation mechanism, namely the intergranular stress corrosion cracking. This is the major degradation mechanism in old stainle...
A horizontal pipe in the water level control system of a power plant boiler failed in service at a t...
Risk-Informed In-Service Inspection (RI-ISI) aims at prioritizing the components for inspection with...
The assessment of initial cracks for Risk Informed In-Service Inspection (RI-ISI) analyses of Nuclea...
This paper describes the comparative study of two approaches to estimate pipe leak and rupture frequ...
The report describes the comparative study of two approaches to estimate pipe leak and rupture frequ...
The report describes the comparative study of two approaches to estimate pipe leak and rupture frequ...
Piping failure frequencies are needed e.g. for quantifying initiating event frequencies in probabili...
The primary source of in-service degradation of the SRS production reactor process water piping is i...
During the past 25 years, in the context of probabilistic safety assessment, efforts have been direc...
The work described in this report applies probabilistic structural mechanics models to predict the r...
Leakages and ruptures of piping components lead to reduction or loss of the pressure retaining capab...
AbstractThe leak before break (LBB) concept is widely used in designing pipe lines in nuclear power ...
Regulatory Guide 1.45, {open_quotes}Reactor Coolant Pressure Boundary Leakage Detection Systems,{clo...
Sandia National Laboratories (SNL) participated in a Pilot Study to examine the process and requirem...
This report presents a summary of a three years long study on the failure probabilities of nuclear p...
A horizontal pipe in the water level control system of a power plant boiler failed in service at a t...
Risk-Informed In-Service Inspection (RI-ISI) aims at prioritizing the components for inspection with...
The assessment of initial cracks for Risk Informed In-Service Inspection (RI-ISI) analyses of Nuclea...
This paper describes the comparative study of two approaches to estimate pipe leak and rupture frequ...
The report describes the comparative study of two approaches to estimate pipe leak and rupture frequ...
The report describes the comparative study of two approaches to estimate pipe leak and rupture frequ...
Piping failure frequencies are needed e.g. for quantifying initiating event frequencies in probabili...
The primary source of in-service degradation of the SRS production reactor process water piping is i...
During the past 25 years, in the context of probabilistic safety assessment, efforts have been direc...
The work described in this report applies probabilistic structural mechanics models to predict the r...
Leakages and ruptures of piping components lead to reduction or loss of the pressure retaining capab...
AbstractThe leak before break (LBB) concept is widely used in designing pipe lines in nuclear power ...
Regulatory Guide 1.45, {open_quotes}Reactor Coolant Pressure Boundary Leakage Detection Systems,{clo...
Sandia National Laboratories (SNL) participated in a Pilot Study to examine the process and requirem...
This report presents a summary of a three years long study on the failure probabilities of nuclear p...
A horizontal pipe in the water level control system of a power plant boiler failed in service at a t...
Risk-Informed In-Service Inspection (RI-ISI) aims at prioritizing the components for inspection with...
The assessment of initial cracks for Risk Informed In-Service Inspection (RI-ISI) analyses of Nuclea...