SCALE/AMPX multigroup libraries for sodium-cooled fast reactor systems

Friederike Bostelmann, Bradley T. Rearden, Winfried Zwermann, Andreas Pautz

Research output: Contribution to journalArticlepeer-review

3 Scopus citations

Abstract

New multigroup cross section libraries and associated covariance files that are optimized for the analysis of sodium-cooled fast reactors were generated with the AMPX tools distributed with the SCALE code system. These new libraries account for the fast neutron flux spectrum with sufficient resolution of resonances in the higher energy range to reproduce continuous-energy reference results and to provide the basis for sensitivity and uncertainty analyses of fast spectrum systems with the SCALE code system. The performance of the new libraries was investigated in terms of the eigenvalue, the neutron flux and reaction rates in criticality calculations, and the generation of group constants. A library using 302 energy groups and a fast neutron flux spectrum as the weighting function led to very good agreement with reference continuous-energy results. The performance of the new library was demonstrated in calculations of experiments from the International Criticality Safety Benchmark Evaluation Project handbook.

Original languageEnglish
Article number107102
JournalAnnals of Nuclear Energy
Volume140
DOIs
StatePublished - Jun 1 2020

Funding

The ORNL contributions to this work were jointly sponsored by the US Department of Energy's Office of Nuclear Energy and the US Nuclear Regulatory Commission Office of Nuclear Regulatory Research. The GRS part of this work is supported by the German Federal Ministry for Economic Affairs and Energy . The ORNL contributions to this work were jointly sponsored by the US Department of Energy's Office of Nuclear Energy and the US Nuclear Regulatory Commission Office of Nuclear Regulatory Research. The GRS part of this work is supported by the German Federal Ministry for Economic Affairs and Energy.

Keywords

  • Multigroup library
  • SCALE
  • SFR-UAM
  • Sodium-cooled fast reactor

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