Impact of nuclear data on sodium-cooled fast reactor calculations

Neutron transport and depletion calculations are performed in combination with various nuclear data libraries in order to assess the impact of nuclear data on safety-relevant parameters of sodium-cooled fast reactors. These calculations are supplemented by systematic uncertainty analyses with respec...

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Bibliographic Details
Published inEPJ Web of Conferences Vol. 111; p. 11003
Main Authors Aures, Alexander, Bostelmann, Friederike, Zwermann, Winfried, Velkov, Kiril
Format Journal Article Conference Proceeding
LanguageEnglish
Published Les Ulis EDP Sciences 01.01.2016
Subjects
Fast nuclear reactors
Libraries
Mathematical analysis
Multiplication
Nuclear engineering
Nuclear safety
Parameter uncertainty
Sodium cooled reactors
Uncertainty analysis
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Summary:Neutron transport and depletion calculations are performed in combination with various nuclear data libraries in order to assess the impact of nuclear data on safety-relevant parameters of sodium-cooled fast reactors. These calculations are supplemented by systematic uncertainty analyses with respect to nuclear data. Analysed quantities are the multiplication factor and nuclide densities as a function of burn-up and the Doppler and Na-void reactivity coefficients at begin of cycle. While ENDF/B-VII.0 / -VII.1 yield rather consistent results, larger discrepancies are observed between the JEFF libraries. While the newest evaluation, JEFF-3.2, agrees with the ENDF/B-VII libraries, the JEFF-3.1.2 library yields significant larger multiplication factors.
ISSN:2100-014X
2101-6275
2100-014X
DOI:10.1051/epjconf/201611111003