研究论文

Numerical and experimental analysis of LBE flow and heat transfer characteristics in hexagonal rod bundles

Xingguang Zhou, Dalin Zhang, Jie Liu, Chao Lin, Liang Yu, Wenxi Tian, Suizheng Qiu, Guanghui Su

Xi'an Jiaotong University　China Institute of Atomic Energy

来源Annals of Nuclear Energy

年份2023

DOI10.1016/j.anucene.2023.109846

原文https://doi.org/10.1016/j.anucene.2023.109846

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Heat transfer and supercritical fluids · Nuclear Engineering Thermal-Hydraulics

参考文献 37

HLM fuel pin bundle experiments in the CIRCE pool facility

Daniele Martelli, Nicola Forgione, I. Di Piazza · Nuclear Engineering and Design · 2015

被引 43

The core design of ALFRED, a demonstrator for the European lead-cooled reactors

Giacomo Grasso, C. Petrovich, Davide Mattioli · Nuclear Engineering and Design · 2014

被引 175

Preliminary conceptual design of a lead–bismuth cooled small reactor (CLEAR-SR)

Minhuang Wang, Chao Lian, Yuanye Li · International Journal of Hydrogen Energy · 2015

被引 51

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引用本文 36

Evaluation of a numerical model for predicting flow and heat transfer in a hexagonal helical cruciform seven-rods bundle and analysis of rod bundle size independence

Dianqiang Jiang, Jian Deng, Da‐Lin Zhang · International Communications in Heat and Mass Transfer · 2024

被引 16

S-CO2 and LBE coupled heat transfer characteristics analysis in new layout PCHE

Kai Liu, Fulong Zhao, Yang Ming · Nuclear Engineering and Design · 2024

被引 15

Subchannel thermal–hydraulic analysis of a wire-wrapped 19-pin rod bundle in the NACIE-UP facility

Rong Zhang, Dalin Zhang, Liang Yu · Annals of Nuclear Energy · 2023

被引 14

按被引量排序，此处列出前 3 条