BUCHARD, M. Guillaume (2024) Validation of the CATHARE 3 modelling on the SCTF experiments PFE - Project Graduation, ENSTA.
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Abstract
The Loss Of Coolant Accident (LOCA) is one of the accidents studied for Pressurized Water Reactors (PWR) safety reports. Depending on the breach size, the cooling of nuclear fuel may deteriorate, leading to the fusion of fuel cladding: containment of radioactive material is not guaranteed anymore. Several safety mechanisms (reactor shutdown, safety injection) aim at limiting the consequences of the loss of coolant, and reactors are designed to avoid core fusion. Thermal-hydraulics scientific calculation tools should be able to accurately compute the physical phenomena that occur during a LOCA. Such phenomena are complex because of crossflows, turbulences, and the two-phase nature of the flow. The current report presents the studies, lead during the internship, to assess the validity of the crossflows calculated with CATHARE 3, a two-phase flow code developed to model reactor systems, during the reflooding phase of a LOCA. This work is based on the CATHARE 3 modeling of the Slab Core Test Facility (SCTF). It includes an analysis of CATHARE 3 reflooding module and the implementation of the reflooding-related physical parameters, the sensitivity tests that have been performed to compare results of the flow computations and experimental data, as well as the analysis of crossflows simulation with CATHARE 3.
Item Type: | Thesis (PFE - Project Graduation) |
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Uncontrolled Keywords: | Loss Of Coolant Accident (LOCA), Reflooding, SCTF, CATHARE 3 |
Subjects: | Fluid Mechanics and Energy |
ID Code: | 10427 |
Deposited By: | Guillaume BUCHARD |
Deposited On: | 09 oct. 2024 19:30 |
Dernière modification: | 09 oct. 2024 19:30 |
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