Author:
Yang Bao-Wen,Ninokata Hisashi,Long Jianping,Liu Aiguo,Han Bin
Subject
Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Reference196 articles.
1. Avramova, M.N., R.K. Salko (2016). CTF Theory Manual, US Department of Energy-CASL: 126-134.
2. Avramova, M. (2007). Development of an innovative spacer grid model utilizing computational fluid dynamics within a subchannel analysis tool, The Pennsylvania State University. Doctor of Philosophy.
3. Comparative Analysis of CTF and Trace Thermal-Hydraulic Codes Using OECD/NRC PSBT Benchmark Void Distribution Database;Avramova;Sci. Technol. Nucl. Install.,2013
4. Assessment of CTF Boiling Transition and Critical Heat Flux Modeling Capabilities Using the OECD/NRC BFBT and PSBT Benchmark Databases;Avramova;Sci. Technol. Nucl. Install.,2013
5. Aydogan, F.,Hochreiter, L.E. et al. (2006). Evaluation of the Sub-Channel Code COBRA-TF for Prediction of BWR Fuel Assembly Void Fraction Distribution. 14th International Conference on Nuclear Engineering (ICONE-14). Miami, Florida, USA.
Cited by
9 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