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RISS 인기검색어
- 검색키워드
- 저자 : B. Krzykacz-Hausmann (검색결과 3 건)
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Uncertainty Analyses with Nuclear Covariance Ddata in Reactor Core Ccalculations
W. Zwermann,B. Krzykacz-Hausmann,L. Gallner,A. Pautz,M. Mattes 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
To investigate the influence of nuclear data uncertainties on the core power distributions systematically, the uncertainty and sensitivity software package SUSA developed at GRS was extended for the use with nuclear covariance data. Varied nuclear data are generated randomly corresponding to the uncertainty information from the covariance matrices. After performing a large number of calculations with these data, the results are statistically evaluated; this can be done not only with integral, but also differential output quantities like the assembly power distribution. The method is applied to multi-group Monte Carlo calculations for the PWR MOX/UO<sub>2</sub> benchmark core. The uncertainty in the resulting k-eff turns out to be of the same order as for pin cell calculations. Unexpectedly large uncertainties result for the normalized radial power distribution. The relative 1σ-uncertainties in the central and peripheral assembly powers are of the order of 4%. The dominating contribution is the uncertainty in the number of neutrons per fission of ^(239)Pu; therefore, the effect is particularly pronounced in a UO_2/MOX core with a high amount of ^(239)Pu in the isotopic composition.
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W. ZWERMANN,A. AURES,L. Gallner,V. HANNSTEIN,B. Krzykacz-Hausmann,K. VELKOV,J.S. MARTINEZ 한국원자력학회 2014 Nuclear Engineering and Technology Vol.46 No.3
Uncertainty and sensitivity analyses with respect to nuclear data are performed with depletion calculations for BWR andPWR fuel assemblies specified in the framework of the UAM-LWR Benchmark Phase II. For this, the GRS sampling basedtool XSUSA is employed together with the TRITON depletion sequences from the SCALE 6.1 code system. Uncertainties formultiplication factors and nuclide inventories are determined, as well as the main contributors to these result uncertainties bycalculating importance indicators. The corresponding neutron transport calculations are performed with the deterministicdiscrete-ordinates code NEWT. In addition, the Monte Carlo code KENO in multi-group mode is used to demonstrate amethod with which the number of neutron histories per calculation run can be substantially reduced as compared to that in acalculation for the nominal case without uncertainties, while uncertainties and sensitivities are obtained with almost the sameaccuracy.
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Zwermann, W.,Aures, A.,Gallner, L.,Hannstein, V.,Krzykacz-Hausmann, B.,Velkov, K.,Martinez, J.S. Korean Nuclear Society 2014 Nuclear Engineering and Technology Vol.46 No.3
Uncertainty and sensitivity analyses with respect to nuclear data are performed with depletion calculations for BWR and PWR fuel assemblies specified in the framework of the UAM-LWR Benchmark Phase II. For this, the GRS sampling based tool XSUSA is employed together with the TRITON depletion sequences from the SCALE 6.1 code system. Uncertainties for multiplication factors and nuclide inventories are determined, as well as the main contributors to these result uncertainties by calculating importance indicators. The corresponding neutron transport calculations are performed with the deterministic discrete-ordinates code NEWT. In addition, the Monte Carlo code KENO in multi-group mode is used to demonstrate a method with which the number of neutron histories per calculation run can be substantially reduced as compared to that in a calculation for the nominal case without uncertainties, while uncertainties and sensitivities are obtained with almost the same accuracy.
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