Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
8068253 | Annals of Nuclear Energy | 2015 | 18 Pages |
Abstract
To meet the simulation needs of its LOCA R&D program, the IRSN is developing a multi-rod computational tool named DRACCAR. In order to realistically describe the behavior of the reactor core during a Loss Of Coolant Accident (LOCA), modeling has to take into account many coupled phenomena such as thermics (heat generation, radiation, convection and conduction), hydraulics (multi dimensional 1-3 phase flow, shrinkage), mechanics (thermal dilatation, creep, embrittlement) and chemistry (oxidation, oxygen diffusion, hydriding,...). This paper presents several aspects of the DRACCAR code abilities: first to handle thermal-hydraulics during reflooding of an intact and of a partially ballooned bundle and secondly the simulation of the OECD SFP phase II experiment dealing with the instantaneous draining of a spent fuel pool.
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Authors
S. Bascou, O. De Luze, S. Ederli, G. Guillard,