Development of a subchannel analysis code and its application to annular fuel assemblies
Author:
Funder
National Natural Science Foundation of China
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference14 articles.
1. Design of annular fuels for a typical VVER-1000 core: Neutronic investigation, pitch optimation and MDNBR calculation;Amin Mozafari;Ann. Nucl. Energy,2013
2. Prospectsfor using annular fuel elements in nuclear power engineering;Blinkov;Therm. Eng.,2010
3. Mechanism study and theoretical simulation on heat split phenomenon in dual-cooled annular fuel element;Deng;Ann. Nucl. Energy,2016
4. Development of a thermal–mechanical behavior coupling analysis code for a dual-cooled annular fuel element in PWRs;Deng;Nucl. Eng. Des.,2016
5. Thermal-hydraulic design of high power density annular fuel in PWRs;Feng;Nucl. Technol.,2007
Cited by 10 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 study on the effect of lateral vibration frequency on the flow and heat transfer characteristics inside annular fuel elements;Thermal Science and Engineering Progress;2024-05
2. Experimental study on flow split and pressure drop characteristics in a 3 × 3 dual-cooled annular rod bundle;Annals of Nuclear Energy;2023-12
3. Experimental study on coupled quenching behavior in a dual-cooled annular rod channel;Progress in Nuclear Energy;2023-10
4. Numerical Study of the Flow and Heat Transfer Characteristics within an Annular Fuel Element Under Lateral Vibration Conditions;2023
5. Development of subchannel thermal-hydraulic analysis code for dual cooled annular fuel;Progress in Nuclear Energy;2022-08
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