Applicability of RANS models and pressure drop in edge subchannels for 19-pin wire-wrapped fuel bundle channel in CiADS
Dajun Fan,
Rongjie Li,
Ruoxiang Qiu,
Minghan He,
Jiatai Liu,
Yanze Tang,
Lu Zhang,
Dawei Cui,
Liming Zhu,
Long Gu,
Yue Li
Affiliations
Dajun Fan
Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou, 730000, China; School of Nuclear Science and Technology, University of Chinese Academy of Sciences, Beijing, 100049, China; Advanced Energy Science and Technology Guangdong Laboratory, Huizhou, 516003, China
Rongjie Li
Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou, 730000, China; School of Nuclear Science and Technology, University of Chinese Academy of Sciences, Beijing, 100049, China
Ruoxiang Qiu
China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen, 518000, China
Minghan He
Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou, 730000, China; School of Nuclear Science and Technology, University of Chinese Academy of Sciences, Beijing, 100049, China
Jiatai Liu
Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou, 730000, China; School of Nuclear Science and Technology, University of Chinese Academy of Sciences, Beijing, 100049, China
Yanze Tang
Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou, 730000, China; School of Nuclear Science and Technology, University of Chinese Academy of Sciences, Beijing, 100049, China; Advanced Energy Science and Technology Guangdong Laboratory, Huizhou, 516003, China
Lu Zhang
Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou, 730000, China; School of Nuclear Science and Technology, University of Chinese Academy of Sciences, Beijing, 100049, China
Dawei Cui
China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen, 518000, China
Liming Zhu
Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou, 730000, China; School of Nuclear Science and Technology, University of Chinese Academy of Sciences, Beijing, 100049, China
Long Gu
Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou, 730000, China; School of Nuclear Science and Technology, University of Chinese Academy of Sciences, Beijing, 100049, China; School of Nuclear Science and Technology, Lanzhou University, Lanzhou, 730000, China; Corresponding author. Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China.
Yue Li
Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou, 730000, China; Corresponding author.
The accelerator-driven subcritical system has a strong transmutation ability and high inherent safety, and it is internationally recognized as the most promising long-life nuclear waste disposal device. This study involves the construction of a Visual Hydraulic ExperimentaL Platform (VHELP) for the purpose of evaluating the applicability of Reynolds-averaged Navier–Stokes (RANS) models and analyzing the pressure distribution within the fuel bundle channel of China initiative accelerator-driven system (CiADS). Measurements of thirty differential pressures in edge subchannels within a 19-pin wire-wrapped fuel bundle channel were obtained under different conditions using deionized water. The pressure distribution in the fuel bundle channel at Reynolds numbers of 5000, 7500, 10,000, 12,500, and 15,000 was simulated using Fluent. The results show that RANS models obtained accurate results, and the shear stress transport k-ω model provided the most accurate prediction of the pressure distribution. The difference between the results of the Shear stress transport (SST) k-ω model and experimental data was the smallest, and the maximum difference was ±5.57%. Moreover, the error between the experimental data and numerical results of the axial differential pressure was smaller than that of the transverse differential pressure. The pressure periodicity in axial and transverse directions (one pitch) and a relatively three-dimensional pressure measurements were studied. The static pressure fluctuated and decreased periodically as the z-axis coordinate increased. These results can facilitate research on the cross-flow characteristics of liquid metal-cooled fast reactors.
