Analysis of the performances of the CFD schemes used for coupling computation

Guangliang Chen; Hongwei Jiang; Huilun Kang; Rui Ma; Lei Li; Yang Yu; Xiaochang Li

doi:https://doi.org/10.1016/j.net.2021.01.006

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자료유형: 학술저널

저자정보: Guangliang Chen (Harbin Engineering University) Hongwei Jiang (Harbin Engineering University) Huilun Kang (Harbin Engineering University) Rui Ma (China Ship Development and Design Center) Lei Li (Harbin Engineering University) Yang Yu (Nuclear Power Institute of China) Xiaochang Li (Harbin Engineering University)

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제53권 제7호

발행연도: 2021.7

수록면: 2,162 - 2,173 (12page)

DOI: https://doi.org/10.1016/j.net.2021.01.006

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In this paper, the coupling of fine-mesh computational fluid dynamics (CFD) thermal-hydraulics (TH)code and neutronics code is achieved using the Ansys Fluent User Defined Function (UDF) for codedevelopment, including parallel meshing mapping, data computation, and data transfer. Also, some CFDschemes are designed for mesh mapping and data transfer to guarantee physical conservation in thecoupling computation. Because there is no rigorous research that gives robust guidance on the variousCFD schemes that must be obtained before the fine-mesh coupling computation, this work presents aquantitative analysis of the CFD meshing and mapping schemes to improve the accuracy of the value andlocation of key physical prediction. Furthermore, the effect of the sub-pin scale coupling computation isalso studied. It is observed that even the pin-resolved coupling computation can also create a largedeviation in the maximum value and spatial locations, which also proves the significance of the researchon mesh mapping and data transfer for CFD code in a coupling computation

#Thermal hydraulics #CFD schemes #PWR

참고문헌 (19)

참고문헌 신청

Y. Ma / 2019 / RMC/CTF multiphysics solutions to VERA core physics benchmark problem 9 / Ann. Nucl. Energy 133:837~852

A. M. Ward / 2020 / Simulated transient behavior of the I2S reactor design / Ann. Nucl. Energy 145:105421

M. Daeubler / 2015 / High-fidelity coupled Monte Carlo neutron transport and thermal-hydraulics simulations using Serpent 2/SUBCHANFLOW / Ann. Nucl. Energy 83:352~375

J. Wang / 2013 / A sub-channel analysis code for advanced lead bismuth fast reactor / Prog. Nucl. Energy 63:34~48

M. Daeubler / 2015 / Static and transient pin-by-pin simulations of a full PWR core with the extended coupled code system DYNSUB / Ann. Nucl. Energy 84:31~44

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