Comparative neutronics analysis of dimple S06 benchmark

Wonkyeong Kim, Jinsu Park, Deokjung Lee, Tomasz Kozlowski

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

The DIMPLE S06 critical benchmark has been calculated using a direct modeling and a two-step modeling approaches. A direct modeling is performed with MCNP6, SERPENT2, CASM04E, and TRITON/NEWT. A two-step modeling is performed by using the nodal code PARCS3.0 employing the homogenized two-group cross section which are generated through SERPENT2, CASM04E and TRITON/NEWT. Detailed calculation models are developed in this paper and the parameters for a two-step modeling generated by each code are compared to each other. Finally, the eigenvalue for DIMPLE S06 are compared to each a direct and a two-step modeling. In this paper, the calculation result of two-step modeling agrees well with that of direct modeling. The result shows that the use of the assembly discontinuity factor in two-step calculation is essential to improve the relative error to the result of a direct modeling. A necessity of the assembly discontinuity factor is clearly proved by calculating the flux distribution for the homogenized assembly.

Original languageEnglish (US)
Title of host publication5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015
Subtitle of host publicationAdvances in Nuclear Fuel Management V
PublisherAmerican Nuclear Society
Pages416-431
Number of pages16
ISBN (Electronic)9781510808034
StatePublished - Jan 1 2015
Event5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015 - Hilton Head, United States
Duration: Mar 29 2015Apr 1 2015

Publication series

Name5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel Management V

Other

Other5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015
CountryUnited States
CityHilton Head
Period3/29/154/1/15

Fingerprint

Fluxes

Keywords

  • ADF
  • Assembly homogenized cross section
  • DIMPLE S06
  • Nodal calculation

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Fuel Technology
  • Energy Engineering and Power Technology

Cite this

Kim, W., Park, J., Lee, D., & Kozlowski, T. (2015). Comparative neutronics analysis of dimple S06 benchmark. In 5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel Management V (pp. 416-431). (5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel Management V). American Nuclear Society.

Comparative neutronics analysis of dimple S06 benchmark. / Kim, Wonkyeong; Park, Jinsu; Lee, Deokjung; Kozlowski, Tomasz.

5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel Management V. American Nuclear Society, 2015. p. 416-431 (5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel Management V).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Kim, W, Park, J, Lee, D & Kozlowski, T 2015, Comparative neutronics analysis of dimple S06 benchmark. in 5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel Management V. 5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel Management V, American Nuclear Society, pp. 416-431, 5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015, Hilton Head, United States, 3/29/15.
Kim W, Park J, Lee D, Kozlowski T. Comparative neutronics analysis of dimple S06 benchmark. In 5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel Management V. American Nuclear Society. 2015. p. 416-431. (5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel Management V).
Kim, Wonkyeong ; Park, Jinsu ; Lee, Deokjung ; Kozlowski, Tomasz. / Comparative neutronics analysis of dimple S06 benchmark. 5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel Management V. American Nuclear Society, 2015. pp. 416-431 (5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel Management V).
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