Development of thermal hydraulic analysis code of annular fuel under flow blockage condition
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference12 articles.
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2. Di Piazza, Ivan, Maguglianib, Fabrizio, Tarantinoa, Mariano, Alemberti, Alessandro, 2014. A CFD analysis of flow blockage phenomena in ALFRED LFR demo fuel assembly. Nucl. Eng. Design 276, 202–215.
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4. Development of a subchannel analysis code and its application to annular fuel assemblies;Xia;Ann. Nucl. Energy,2019
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2. Numerical study of the flow and heat transfer characteristics within the annular fuel element with double-sided cooling;Annals of Nuclear Energy;2024-05
3. Experimental study on coupled quenching behavior in a dual-cooled annular rod channel;Progress in Nuclear Energy;2023-10
4. Modeling hot channel two-phase flow of PWR NPPs during abnormal condition, using Python;Nuclear Engineering and Design;2023-08
5. Study on the safety characteristics of molten corium in-vessel retention of annular fuel core;Annals of Nuclear Energy;2023-06
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