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Assessment of subchannel flow mixing coefficients for wire-wrapped hexagonal fuel rod bundlesopen access

Authors
Choi, Sun RockKim, HyungmoChang, Seok-KyuChoi, Hae SeobEuh, Dong-JinLee, Hyeong-YeonYang, Won Sik
Issue Date
Feb-2022
Publisher
PERGAMON-ELSEVIER SCIENCE LTD
Keywords
Subchannel flow mixing; ENERGY model; Sodium-cooled fast reactor; Core thermal-hydraulics
Citation
ANNALS OF NUCLEAR ENERGY, v.166
Indexed
SCIE
SCOPUS
Journal Title
ANNALS OF NUCLEAR ENERGY
Volume
166
URI
https://scholarworks.bwise.kr/gnu/handle/sw.gnu/1661
DOI
10.1016/j.anucene.2021.108810
ISSN
0306-4549
Abstract
Flow mixing between adjacent subchannels within a wire-wrapped hexagonal fuel rod bundle affects radial heat transfer and determines the maximum cladding temperature, which is a key parameter to ensure the fuel safety margin in a sodium-cooled fast reactor (SFR). In the ENERGY model, both the effec-tive eddy diffusivity and the edge swirl velocity ratio are employed to characterize the subchannel flow mixing. The Korea Atomic Energy Research Institute conducted subchannel flow mixing tests on the 37 -pin and 61-pin bundle assemblies. The test assemblies were fabricated by reflecting thermal-hydraulic similarities of the Prototype Gen-IV SFR candidate cores. The subchannel flow mixing experiment was conducted using a wire-mesh sensing system. The subchannel flow mixing coefficients are determined by the least-square method so that the difference between the SLTHEN code prediction and experimental data is minimized numerically. The results show good agreement with the previous correlations, espe-cially with the Cheng-Todreas model. (c) 2021 The Author(s). Published by Elsevier Ltd. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
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Kim, Hyung Mo
대학원 (기계항공우주공학부)
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