Development of a multi-physics calculation platform dedicated to irradiation devices in a material testing reactor
- CEA DEN Cadarache, F-13108 St Paul Lez Durances (United States)
- CEA DEN Saclay, F-91190 Gif sur Yvette (France)
- UMR CNRS 6168 LSIS LXAO, F-13288 Marseille Cedex 9 (France)
The physical phenomena involved in irradiation devices within material testing reactors are complex (neutron and photon interactions, nuclear heating, thermal hydraulics, ...). However, the simulation of these phenomena requires a high precision in order to control the condition of the experiment and the development of predictive models. Until now, physicists use different tools with several approximations at each interface. The aim of this work is to develop a calculation platform dedicated to numerical multi-physics simulations of irradiation devices in the future European Jules Horowitz Reactor [1], This platform is based on a multi-physics data model which describes geometries, materials and state parameters associated with a sequence of thematic (neutronics, thermal hydraulics...) computations of these devices. Once the computation is carried out, the results can be returned to the data model (DM). The DM is encapsulated in a dedicated module of the SALOME platform [2] and exchanges data with SALOME native modules. This method allows a parametric description of a study, independent of the code used to perform the simulation. The application proposed in this paper concerns neutronic calculation of a fuel irradiation device with the new method of characteristics implemented in the APOLLO2 code [3]. The device is located at the periphery of the OSIRIS core. This choice is motivated by the possibility to compare the calculation with experimental results, which cannot be done for the Jules Horowitz Reactor, currently in design study phase. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 22039465
- Resource Relation:
- Conference: PHYSOR-2006: American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation, Vancouver, BC (Canada), 10-14 Sep 2006; Other Information: Country of input: France; 12 refs.
- Country of Publication:
- United States
- Language:
- English
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