File Download

There are no files associated with this item.

  • Find it @ UNIST can give you direct access to the published full text of this article. (UNISTARs only)
Related Researcher

이덕중

Lee, Deokjung
Computational Reactor physics & Experiment Lab.
Read More

Views & Downloads

Detailed Information

Cited time in webofscience Cited time in scopus
Metadata Downloads

Full metadata record

DC Field Value Language
dc.citation.conferencePlace US -
dc.citation.conferencePlace Hilton Head -
dc.citation.endPage 431 -
dc.citation.startPage 416 -
dc.citation.title 5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015 -
dc.contributor.author Kim, Wonkyeong -
dc.contributor.author Park, Jinsu -
dc.contributor.author Lee, Deokjung -
dc.contributor.author Kozlowski, Tomasz -
dc.date.accessioned 2023-12-19T22:39:51Z -
dc.date.available 2023-12-19T22:39:51Z -
dc.date.created 2015-11-30 -
dc.date.issued 2015-03-29 -
dc.description.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. -
dc.identifier.bibliographicCitation 5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015, pp.416 - 431 -
dc.identifier.isbn 978-151080803-4 -
dc.identifier.scopusid 2-s2.0-84944870547 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/36945 -
dc.language 영어 -
dc.publisher 5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015 -
dc.title Comparative neutronics analysis of dimple S06 benchmark -
dc.type Conference Paper -
dc.date.conferenceDate 2015-03-29 -

qrcode

Items in Repository are protected by copyright, with all rights reserved, unless otherwise indicated.