Flow and heat transfer in reactor core
Prof. Xu Cheng, IATF, KIT CS |
Course |
004 |
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Title |
Flow and heat transfer in reactor core |
Prerequisites |
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Goal of the course |
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Content |
This course deals with thermal-hydraulic modelling in fuel assemblies. It starts with a short introduction of the structure and design criteria of nuclear reactors. Three different approaches of thermal-hydraulic analysis are presented, i.e. single channel approach, sub-channel approach and 3-dimensional approach. For each approach fundamental idea, mathematic background, required closure models will be described. Moreover, merits and shortages of each approach will be discussed. In addition to several application examples, opportunity will be given to students to make exercise with sub-channel analysis codes. |
Lecturer |
Prof. Xu Cheng, IFRT, KIT CS |
Schedule: 4 days |
05.10. - 08.10.2020; 9 am to 5 pm daily |
Location |
KIT-Campus South, Institute for Applied Thermofluidics (IATF) |
Dead line for application: 21.09.2020
Application form download
Prof. Xu Cheng, IATF, KIT CS
Professorship: Innovative Nuclear Systems
Email: xu cheng∂kit edu