Comparative neutronics analysis of DIMPLE S06 criticality benchmark with contemporary reactor core analysis computer code systems

Wonkyeong Kim, Jinsu Park, Tomasz Kozlowski, Hyun Chul Lee, Deokjung Lee

Research output: Contribution to journalArticle

Abstract

A high-leakage core has been known to be a challenging problem not only for a two-step homogenization approach but also for a direct heterogeneous approach. In this paper the DIMPLE S06 core, which is a small high-leakage core, has been analyzed by a direct heterogeneous modeling approach and by a two-step homogenization modeling approach, using contemporary code systems developed for reactor core analysis. The focus of this work is a comprehensive comparative analysis of the conventional approaches and codes with a small core design, DIMPLE S06 critical experiment. The calculation procedure for the two approaches is explicitly presented in this paper. Comprehensive comparative analysis is performed by neutronics parameters: multiplication factor and assembly power distribution. Comparison of two-group homogenized cross sections from each lattice physics codes shows that the generated transport cross section has significant difference according to the transport approximation to treat anisotropic scattering effect. The necessity of the ADF to correct the discontinuity at the assembly interfaces is clearly presented by the flux distributions and the result of two-step approach. Finally, the two approaches show consistent results for all codes, while the comparison with the reference generated by MCNP shows significant error except for another Monte Carlo code, SERPENT2.

Original languageEnglish (US)
Article number180979
JournalScience and Technology of Nuclear Installations
Volume2015
DOIs
StatePublished - Jan 1 2015

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Criticality (nuclear fission)
Core analysis
Reactor cores
Physics
Scattering
Fluxes
Experiments

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

Cite this

Comparative neutronics analysis of DIMPLE S06 criticality benchmark with contemporary reactor core analysis computer code systems. / Kim, Wonkyeong; Park, Jinsu; Kozlowski, Tomasz; Lee, Hyun Chul; Lee, Deokjung.

In: Science and Technology of Nuclear Installations, Vol. 2015, 180979, 01.01.2015.

Research output: Contribution to journalArticle

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