Studies on the subcooled boiling in a fuel assembly with 5 by 5 rods using an improved wall boiling model-Reference-Cited by-同舟云学术

Studies on the subcooled boiling in a fuel assembly with 5 by 5 rods using an improved wall boiling model

Published:2018-04 Issue: Volume:114 Page:413-426
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Cong Tenglong^ORCID,Zhang Rui,Chen Lijuan,Zhang Xiang,Yu Ting

Funder

National Natural Science Foundation of China

Scientific Research Foundation for Youth Scholars of Harbin Engineering University

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference42 articles.

1. ANSYS Inc., 2013. ANSYS FLUENT theory guide. Canonsburg, PA, USA.

2. An experimental investigation of true volumetric vapor content with subcooled boiling in tubes;Bartolomei;Therm. Eng.,1982

3. Experimental study of true void fraction when boiling subcooled water in vertical tubes;Bartolomei;Therm. Eng.,1967

4. A first assessment of the NEPTUNE_CFD code: Instabilities in a stratified flow comparison between the VOF method and a two-field approach;Bartosiewicz;Int. J. Heat Fluid Flow,2008

5. An Experimental Investigation of the Influence of Axial Heat Flux Distributions on Post Dryout Heat Transfer for Flow of Water in Vertical Tubes (KTH-NEL-54);Becker,1992

Cited by 17 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Numerical investigation on critical heat flux for 5 × 5 fuel assemblies with a wide range of working conditions;Progress in Nuclear Energy;2024-04

2. A comprehensive review of numerical and experimental research on the thermal-hydraulics of two-phase flows in vertical rod bundles;International Journal of Heat and Mass Transfer;2024-04

3. Numerical investigation on characteristics of the onset of nucleate boiling in petal-shape fuel rod bundle assembly;Annals of Nuclear Energy;2024-01

4. Numerical study on a semi-mechanistic wall boiling model based on dry-patch mechanism for CHF prediction in vertical tube and fuel assembly;Annals of Nuclear Energy;2023-12

5. An experimental study of boiling two-phase flow in a vertical rod bundle with a spacer grid-Part 2: Effects of vane angle;Experimental Thermal and Fluid Science;2023-11