Light Water Reactor (LWR) core feedback and transient response
Course |
019 |
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Title |
Multi-physics and Multi-scale Methods for the Analysis of Light Water Reactor Core Transients |
Prerequisites |
Fundamentals of Nuclear Engineering |
Goal of the course |
Get familiar with multi-physics methods and tools for the analysis the LWR-core behaviour under transient conditions |
Content |
This training course present the current multi-physics methods for transient analysis of LWR-cores including neutronics, thermal hydraulics and thermo-mechanics. First, the theoretical basis of the involved numerical tools are presented and discussed. It will covers thermal hydraulic sub-channel methods, 3D neutron kinetics, and finally fuel thermo-mechanics. The main physical methods of SUBCHANFLOW (SCF), PARCS and TRANSURANUS (TU) and their simulation capabilities will be discussed. The methodology developed at KIT for the coupling of these three solvers will be also discussed emphasizing its relevance for safety evaluations of LWR-cores. Hands-on-training will include practical exercises (demos) first using the stand-alone codes and the coupled versions of PARCS/SCF and PATCS/SCF/TU. Different problems at sub-channel (SC) and fuel assembly (FA) level will be solved with those coupled codes. For it, the main structure of the input / output of each code as well as the guidelines how to run the codes will be presented and the ways to interpret the main results will be discussed. The demos will include:
The course will be given in English. |
Lecturers:
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Dr. Victor Hugo Sanchez Espinoza (Head of Group Reactor Physics and Dynamics of INR, Lectureship at KIT Mechanical Engineering Faculty on Reactor Safety) Areas of Expertise:
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MSc Luigi Mercatali (INR/RPD, Senior Scientist, Work Package Leader for Code Integration and Coupling Methods within the EU McSAFE Project) Area of expertise:
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Schedule shifted! |
2020; 9 am to 5 pm daily |
Location |
KIT FTU , Buildung 101, Room 221 |
Dead line for application: 2020
Application form download
Physics solvers |
Pin /subchannel Level |
Fuel Assembly level |
N/TH/TM Core Analysis |
Thermal hydraulics |
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Predicted 3D Power Distribution |
Neutronics
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Nodal homogenized |
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Thermo-mechanics |
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Representative TU-model for a FA |