It is sometimes the case in PRA applications that reported plant-specific failure data are, in fact, only estimates which are uncertain. Even for detailed plant-specific data, the reported exposure time or number of demands is often only an estimate of the actual exposure time or number of demands. Likewise the reported number of failure events or incidents is sometimes also uncertain because incident or malfunction reports may be ambiguous. In this report we determine the corresponding uncertainty in core damage frequency which can b attributed to such uncertainties in plant-specific data using a simple but typical nuclear power reactor example
Probabilistic risk assessments (PRA) based on internal initiators are being conducted on a number of...
Sensitivity studies based on Probabilistic Safety Assessments (PSAs) for a pressurized water reactor...
This paper discusses the core damage frequency (CDF) insights gained by analyzing the results of the...
In November 1988, the US Nuclear Regulatory Commission (NRC) issued Generic Letter 88-20 requesting ...
This document contains the appendices for the accident sequence analysis of internally initiated eve...
The work presented in this paper deals with bias and uncertainty quantification on nuclear fuel inve...
One of the most widely used methods to estimate core damage during a nuclear power plant accident is...
The key papers on estimating the uncertainties in nuclear data deal with the influence of these unce...
This document contains the appendices for the accident sequence analysis of internally initiated eve...
The role of human beings in the safe operation of a nuclear power plant has been a matter of concern...
textThis research presents the methodologies used to resolve the Nuclear Regulatory Commission Gener...
The Nuclear Regulatory Commission`s (NRC`s) ongoing Accident Sequence Precursor (ASP) program uses p...
This paper describes an approach that allows the incorporation of various types of uncertainties in ...
AbstractThis paper presents a study of the influence of the uncertainty in the macroscopic neutronic...
The paper demonstrates the influence of uncertainties in microscopic nuclear data on the results of ...
Probabilistic risk assessments (PRA) based on internal initiators are being conducted on a number of...
Sensitivity studies based on Probabilistic Safety Assessments (PSAs) for a pressurized water reactor...
This paper discusses the core damage frequency (CDF) insights gained by analyzing the results of the...
In November 1988, the US Nuclear Regulatory Commission (NRC) issued Generic Letter 88-20 requesting ...
This document contains the appendices for the accident sequence analysis of internally initiated eve...
The work presented in this paper deals with bias and uncertainty quantification on nuclear fuel inve...
One of the most widely used methods to estimate core damage during a nuclear power plant accident is...
The key papers on estimating the uncertainties in nuclear data deal with the influence of these unce...
This document contains the appendices for the accident sequence analysis of internally initiated eve...
The role of human beings in the safe operation of a nuclear power plant has been a matter of concern...
textThis research presents the methodologies used to resolve the Nuclear Regulatory Commission Gener...
The Nuclear Regulatory Commission`s (NRC`s) ongoing Accident Sequence Precursor (ASP) program uses p...
This paper describes an approach that allows the incorporation of various types of uncertainties in ...
AbstractThis paper presents a study of the influence of the uncertainty in the macroscopic neutronic...
The paper demonstrates the influence of uncertainties in microscopic nuclear data on the results of ...
Probabilistic risk assessments (PRA) based on internal initiators are being conducted on a number of...
Sensitivity studies based on Probabilistic Safety Assessments (PSAs) for a pressurized water reactor...
This paper discusses the core damage frequency (CDF) insights gained by analyzing the results of the...