Validation of CATHARE 3D module on LSTF core
Résumé
CATHARE is the French thermal-hydraulic code for safety analysis of nuclear reactors. Its three-dimensional (3-D) module is mainly used to model the reactor vessel where 3D effects occur during a loss-of-coolant accident (LOCA).
The OECD/NEA ROSA-2 Project Test 3 (SB-HL-18 in JAEA) was conducted with the Large Scale Test Facility (LSTF). This test simulated a PWR 1.5% hot-leg Small Break Lost Of Coolant Accident (SB-LOCA). During this test, the core uncovers twice.
A 3D modeling of the LSTF core has been made with CATHARE code, and the experimental evolutions at the core boundary during the core uncovery phases of Test 3 have been reproduced in the calculations. This paper will compare the experimental evolutions of the cladding temperature with the calculation results during the core uncovery phases.
The results show that the 3D module of the CATHARE code is validated to deal with Intermediate Break LOCA (IB-LOCA) core uncovery accidental situations which is essential in safety studies. No shortcoming is associated with the use of closure relations (interfacial friction in rod bundle geometry and wall to vapor heat flux) taken from a 1-D model. This article will also show that in a PWR accidental
situation with a core uncover phase, the use of a 3-D modeling of the core is necessary because of 3D effects occurring in the core.
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