Comparative Neutronics Analysis of DIMPLE S06 Criticality Benchmark with Contemporary Reactor Core Analysis Computer Code Systems
Joint Authors
Kozlowski, Tomasz
Kim, Wonkyeong
Park, Jinsu
Lee, Hyun Chul
Lee, Deokjung
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2015, Issue 2015 (31 Dec. 2015), pp.1-11, 11 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2015-07-28
Country of Publication
Egypt
No. of Pages
11
Abstract EN
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.
American Psychological Association (APA)
Kim, Wonkyeong& Park, Jinsu& Kozlowski, Tomasz& Lee, Hyun Chul& Lee, Deokjung. 2015. Comparative Neutronics Analysis of DIMPLE S06 Criticality Benchmark with Contemporary Reactor Core Analysis Computer Code Systems. Science and Technology of Nuclear Installations،Vol. 2015, no. 2015, pp.1-11.
https://search.emarefa.net/detail/BIM-1077818
Modern Language Association (MLA)
Kim, Wonkyeong…[et al.]. Comparative Neutronics Analysis of DIMPLE S06 Criticality Benchmark with Contemporary Reactor Core Analysis Computer Code Systems. Science and Technology of Nuclear Installations No. 2015 (2015), pp.1-11.
https://search.emarefa.net/detail/BIM-1077818
American Medical Association (AMA)
Kim, Wonkyeong& Park, Jinsu& Kozlowski, Tomasz& Lee, Hyun Chul& Lee, Deokjung. Comparative Neutronics Analysis of DIMPLE S06 Criticality Benchmark with Contemporary Reactor Core Analysis Computer Code Systems. Science and Technology of Nuclear Installations. 2015. Vol. 2015, no. 2015, pp.1-11.
https://search.emarefa.net/detail/BIM-1077818
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-1077818