Experimental determination and analysis of the transverse pressure difference in a wire-wrapped rod bundle
出版年份 2021 全文链接
标题
Experimental determination and analysis of the transverse pressure difference in a wire-wrapped rod bundle
作者
关键词
Transverse pressure difference, Wire-wrapped rod bundles, Reynolds number, Hexagonal duct
出版物
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER
Volume 170, Issue -, Pages 120958
出版商
Elsevier BV
发表日期
2021-02-04
DOI
10.1016/j.ijheatmasstransfer.2021.120958
参考文献
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- (2018) S.K. Chen et al. NUCLEAR ENGINEERING AND DESIGN
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- Heat transfer from a 2 × 2 wire-wrapped rod bundle to supercritical pressure water
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- Benchmark exercise for fluid flow simulations in a liquid metal fast reactor fuel assembly
- (2016) E. Merzari et al. NUCLEAR ENGINEERING AND DESIGN
- Numerical implementation of the Cheng and Todreas correlation for wire wrapped bundle friction factors-desirable improvements in the transition flow region
- (2013) S.K. Chen et al. NUCLEAR ENGINEERING AND DESIGN
- Evaluation of existing correlations for the prediction of pressure drop in wire-wrapped hexagonal array pin bundles
- (2013) S.K. Chen et al. NUCLEAR ENGINEERING AND DESIGN
- Experimental and numerical study of convective heat transfer and fluid flow in twisted oval tubes
- (2012) Xiang-hui Tan et al. INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER
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