Investigation on heat transfer non-uniformity in rod bundle-Reference-Cited by-同舟云学术

Investigation on heat transfer non-uniformity in rod bundle

Published:2013-12 Issue: Volume:265 Page:222-231
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Yang T.,Liu X.J.,Cheng X.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference24 articles.

1. A mixed core for supercritical water-cooled reactors;Cheng;Nucl. Eng. Technol.,2008

2. CFD analysis of thermal–hydraulic behavior of heavy liquid metals in sub-channels;Cheng;Nucl. Eng. Des.,2006

3. Local thermal-hydraulic behaviour in tight 7-rod bundles;Cheng;Nucl. Eng. Des.,2009

4. Liquid Metal Fast Breeder Reactor: An Environmental and Economic Critique;Cochran,1974

5. Heat transfer to liquid metals flowing turbulently and longitudinally through closely spaced rod bundles. Part II. Uniform heat flux at the inner surface of the cladding;Dwyer;Nucl. Eng. Des.,1972

Cited by 8 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. Some recent progress in reactor core thermal-hydraulics modelling;Nuclear Engineering and Design;2023-08

2. Subchannel analysis for LMR;Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors;2019

3. A circumferentially non-uniform heat transfer model for subchannel analysis of tight rod bundles;Annals of Nuclear Energy;2018-11

4. Analysis of the influence of pellet-to-cladding gap on the transient heat transfer in nuclear fuel rods via the integral transform technique;Journal of the Brazilian Society of Mechanical Sciences and Engineering;2018-05-25

5. A circumferentially non-uniform fuel model and its application to thermal-hydraulic code;International Journal of Energy Research;2017-05-11