This paper discusses the core damage frequency (CDF) insights gained by analyzing the results of the Individual Plant Examinations (IPES) for two groups of plants: boiling water reactor (BWR) 3/4 plants with Reactor Core Isolation Cooling systems, and Westinghouse 4-loop plants. Wide variability was observed for the plant CDFs and for the CDFs of the contributing accident classes. On average, transients-with loss of injection, station blackout sequences, and transients with loss of decay heat removal are important contributors for the BWR 3/4 plants, while transients, station blackout sequences, and loss-of-coolant accidents are important for the Westinghouse 4-loop plants. The key factors that contribute to the variability in the results a...
It is sometimes the case in PRA applications that reported plant-specific failure data are, in fact,...
In this paper, we report on the core cooling effect by natural circulation cooling of the primary co...
This report revision incorporates new experimental evidence regarding AP600 behavior during small br...
In November 1988, the US Nuclear Regulatory Commission (NRC) issued Generic Letter 88-20 requesting ...
A loss-of-coolant accident (LOCA) can cause a loss-of-offsite power (LOOP) wherein the LOOP is usual...
This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submitta...
[[abstract]]The core damage frequency caused by loss of residual heat removal (RHR) events was asses...
Fault trees (FT) and event trees (ET) are widely used in industry to model and evaluate the reliabil...
The Nuclear Regulatory Commission`s (NRC`s) ongoing Accident Sequence Precursor (ASP) program uses p...
This document contains the appendices for the accident sequence analysis of internally initiated eve...
Operation of pressurised water reactors involves shutdown periods for refuelling and maintenance. In...
Interfacing system loss-of-coolant accidents (ISL) were first identified and analyzed in the Reactor...
Based on level 2 analyses in IPE (Individual Plant Examination) submittals accident progression, per...
This letter report documents models for quantifying the likelihood of loss of spent fuel pool coolin...
This document contains the appendices for the accident sequence analysis of internally initiated eve...
It is sometimes the case in PRA applications that reported plant-specific failure data are, in fact,...
In this paper, we report on the core cooling effect by natural circulation cooling of the primary co...
This report revision incorporates new experimental evidence regarding AP600 behavior during small br...
In November 1988, the US Nuclear Regulatory Commission (NRC) issued Generic Letter 88-20 requesting ...
A loss-of-coolant accident (LOCA) can cause a loss-of-offsite power (LOOP) wherein the LOOP is usual...
This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submitta...
[[abstract]]The core damage frequency caused by loss of residual heat removal (RHR) events was asses...
Fault trees (FT) and event trees (ET) are widely used in industry to model and evaluate the reliabil...
The Nuclear Regulatory Commission`s (NRC`s) ongoing Accident Sequence Precursor (ASP) program uses p...
This document contains the appendices for the accident sequence analysis of internally initiated eve...
Operation of pressurised water reactors involves shutdown periods for refuelling and maintenance. In...
Interfacing system loss-of-coolant accidents (ISL) were first identified and analyzed in the Reactor...
Based on level 2 analyses in IPE (Individual Plant Examination) submittals accident progression, per...
This letter report documents models for quantifying the likelihood of loss of spent fuel pool coolin...
This document contains the appendices for the accident sequence analysis of internally initiated eve...
It is sometimes the case in PRA applications that reported plant-specific failure data are, in fact,...
In this paper, we report on the core cooling effect by natural circulation cooling of the primary co...
This report revision incorporates new experimental evidence regarding AP600 behavior during small br...