Add to ORKGThe objectives of this study on the application of statistical techniques to the analysis of reactor safety codes are the identification of the input variables which have a significant influence on the output variables (sensitivity analysis) and the determination of the effect of uncertainty in input values on the output variables. The Latin hypercube sampling (LHS) procedure is presented as an input value selection procedure. The partial rank correlation coefficient (PRCC) coupled with the LHS procedure is presented as a quantitative measure of sensitivity. An examination of the PRCC variability and an analysis of TRAC for a Semiscale test are presented
The paper presents sensitivity and uncertainty study of Ignalina NPP RBMK-1500 reactor one group dis...
In nuclear safety analysis, it is very important to be able to simulate the different transients tha...
In recent years, more realistic safety analyses of nuclear reactors have been based on best estimate...
A statistical sensitivity analysis procedure has been developed for ranking the input data of large ...
The quantification of uncertainties of various calculation results, caused by the uncertainties asso...
Best-Estimation Plus Uncertainty (BEPU) analysis method can provide more information to improve the ...
MIng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2014This study was based on...
International audienceIn the framework of uncertainty treatment in numerical simulation, Global sens...
This paper presents the application of sensitivity and uncertainty (S/U) analysis methodologies to t...
A NUMBER OF MOSTLY NON-PAREAMETRIC SENSITIVITY ANALYSIS TECHNIQUES ARE COMPARED IN THE ...
In the framework of risk assessment in nuclear accident, simulation tools are widely used to underst...
The use of cross-section covariance data has long been a key part of traditional sensitivity and unc...
Criticality, reactor physics and shielding benchmarks are expected to play important roles in GEN-IV...
Interest in the sensitivity methods that were developed and widely used in the 1970s (the FORSS meth...
An established international expertise in relation to computational tools, procedures for their app...
The paper presents sensitivity and uncertainty study of Ignalina NPP RBMK-1500 reactor one group dis...
In nuclear safety analysis, it is very important to be able to simulate the different transients tha...
In recent years, more realistic safety analyses of nuclear reactors have been based on best estimate...
A statistical sensitivity analysis procedure has been developed for ranking the input data of large ...
The quantification of uncertainties of various calculation results, caused by the uncertainties asso...
Best-Estimation Plus Uncertainty (BEPU) analysis method can provide more information to improve the ...
MIng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2014This study was based on...
International audienceIn the framework of uncertainty treatment in numerical simulation, Global sens...
This paper presents the application of sensitivity and uncertainty (S/U) analysis methodologies to t...
A NUMBER OF MOSTLY NON-PAREAMETRIC SENSITIVITY ANALYSIS TECHNIQUES ARE COMPARED IN THE ...
In the framework of risk assessment in nuclear accident, simulation tools are widely used to underst...
The use of cross-section covariance data has long been a key part of traditional sensitivity and unc...
Criticality, reactor physics and shielding benchmarks are expected to play important roles in GEN-IV...
Interest in the sensitivity methods that were developed and widely used in the 1970s (the FORSS meth...
An established international expertise in relation to computational tools, procedures for their app...
The paper presents sensitivity and uncertainty study of Ignalina NPP RBMK-1500 reactor one group dis...
In nuclear safety analysis, it is very important to be able to simulate the different transients tha...
In recent years, more realistic safety analyses of nuclear reactors have been based on best estimate...