Funder
Ministry of Science and ICT, South Korea
Subject
Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Reference169 articles.
1. FONESYS - The FOrum & NEtwork of SYStem thermal-hydraulic codes in nuclear reactor thermal-hydraulics;Ahn;Nucl. Eng. Des.,2015
2. Development of a new condensation model for the nearly-horizontal heat exchanger tube under the steam flowing conditions;Ahn;Int. J. Heat Mass Transfer,2014
3. Steam condensation in horizontal and inclined tubes under stratified flow conditions;Ahn;Int. J. Heat Mass Transfer,2019
4. An overview on thermal-hydraulic phenomena for water cooled nuclear reactors; part I: SETs, and ITFs of PWRs, BWRs;Aksan;VVERs. Nucl. Eng. Des.,2019
5. An overview on thermal-hydraulic phenomena for water cooled nuclear reactors; part II: ALWRs and SCWRs;Aksan;Nucl. Eng. Des.,2019
Cited by
3 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