Status of XSUSA for Sampling Based Nuclear Data Uncertainty and Sensitivity Analysis

In the present contribution, an overview of the sampling based XSUSA method for sensitivity and uncertainty analysis with respect to nuclear data is given. The focus is on recent developments and applications of XSUSA. These applications include calculations for critical assemblies, fuel assembly de...

Full description

Bibliographic Details
Main Authors: Pasichnyk I., Krzykacz-Hausmann B., Klein M., Gallner L., Zwermann W., Pautz A., Velkov K.
Format: Article
Language:English
Published: EDP Sciences 2013-03-01
Series:EPJ Web of Conferences
Online Access:http://dx.doi.org/10.1051/epjconf/20134203003
id doaj-7996c53c21204b8db240ae74e8973c25
record_format Article
spelling doaj-7996c53c21204b8db240ae74e8973c252021-08-02T16:04:05ZengEDP SciencesEPJ Web of Conferences2100-014X2013-03-01420300310.1051/epjconf/20134203003Status of XSUSA for Sampling Based Nuclear Data Uncertainty and Sensitivity AnalysisPasichnyk I.Krzykacz-Hausmann B.Klein M.Gallner L.Zwermann W.Pautz A.Velkov K.In the present contribution, an overview of the sampling based XSUSA method for sensitivity and uncertainty analysis with respect to nuclear data is given. The focus is on recent developments and applications of XSUSA. These applications include calculations for critical assemblies, fuel assembly depletion calculations, and steadystate as well as transient reactor core calculations. The analyses are partially performed in the framework of international benchmark working groups (UACSA – Uncertainty Analyses for Criticality Safety Assessment, UAM – Uncertainty Analysis in Modelling). It is demonstrated that particularly for full-scale reactor calculations the influence of the nuclear data uncertainties on the results can be substantial. For instance, for the radial fission rate distributions of mixed UO2/MOX light water reactor cores, the 2σ uncertainties in the core centre and periphery can reach values exceeding 10%. For a fast transient, the resulting time behaviour of the reactor power was covered by a wide uncertainty band. Overall, the results confirm the necessity of adding systematic uncertainty analyses to best-estimate reactor calculations. http://dx.doi.org/10.1051/epjconf/20134203003
collection DOAJ
language English
format Article
sources DOAJ
author Pasichnyk I.
Krzykacz-Hausmann B.
Klein M.
Gallner L.
Zwermann W.
Pautz A.
Velkov K.
spellingShingle Pasichnyk I.
Krzykacz-Hausmann B.
Klein M.
Gallner L.
Zwermann W.
Pautz A.
Velkov K.
Status of XSUSA for Sampling Based Nuclear Data Uncertainty and Sensitivity Analysis
EPJ Web of Conferences
author_facet Pasichnyk I.
Krzykacz-Hausmann B.
Klein M.
Gallner L.
Zwermann W.
Pautz A.
Velkov K.
author_sort Pasichnyk I.
title Status of XSUSA for Sampling Based Nuclear Data Uncertainty and Sensitivity Analysis
title_short Status of XSUSA for Sampling Based Nuclear Data Uncertainty and Sensitivity Analysis
title_full Status of XSUSA for Sampling Based Nuclear Data Uncertainty and Sensitivity Analysis
title_fullStr Status of XSUSA for Sampling Based Nuclear Data Uncertainty and Sensitivity Analysis
title_full_unstemmed Status of XSUSA for Sampling Based Nuclear Data Uncertainty and Sensitivity Analysis
title_sort status of xsusa for sampling based nuclear data uncertainty and sensitivity analysis
publisher EDP Sciences
series EPJ Web of Conferences
issn 2100-014X
publishDate 2013-03-01
description In the present contribution, an overview of the sampling based XSUSA method for sensitivity and uncertainty analysis with respect to nuclear data is given. The focus is on recent developments and applications of XSUSA. These applications include calculations for critical assemblies, fuel assembly depletion calculations, and steadystate as well as transient reactor core calculations. The analyses are partially performed in the framework of international benchmark working groups (UACSA – Uncertainty Analyses for Criticality Safety Assessment, UAM – Uncertainty Analysis in Modelling). It is demonstrated that particularly for full-scale reactor calculations the influence of the nuclear data uncertainties on the results can be substantial. For instance, for the radial fission rate distributions of mixed UO2/MOX light water reactor cores, the 2σ uncertainties in the core centre and periphery can reach values exceeding 10%. For a fast transient, the resulting time behaviour of the reactor power was covered by a wide uncertainty band. Overall, the results confirm the necessity of adding systematic uncertainty analyses to best-estimate reactor calculations.
url http://dx.doi.org/10.1051/epjconf/20134203003
work_keys_str_mv AT pasichnyki statusofxsusaforsamplingbasednucleardatauncertaintyandsensitivityanalysis
AT krzykaczhausmannb statusofxsusaforsamplingbasednucleardatauncertaintyandsensitivityanalysis
AT kleinm statusofxsusaforsamplingbasednucleardatauncertaintyandsensitivityanalysis
AT gallnerl statusofxsusaforsamplingbasednucleardatauncertaintyandsensitivityanalysis
AT zwermannw statusofxsusaforsamplingbasednucleardatauncertaintyandsensitivityanalysis
AT pautza statusofxsusaforsamplingbasednucleardatauncertaintyandsensitivityanalysis
AT velkovk statusofxsusaforsamplingbasednucleardatauncertaintyandsensitivityanalysis
_version_ 1721230132332462080