Utveckling av en hybridneutrontranport metod för statiska and dynamiska beräkningar och tillämpning på snabbreaktorsystem
The modelling of neutron transport problems for nuclear reactor systems has long been divided into two types of approaches: the deterministic approach and the probabilistic approach. In the present project, combining the advantage of a probabilistic approach (i.e. high accuracy) and the advantage of a deterministic approach (i.e. low computing cost) is proposed in the development of a new hybrid probabilistic/deterministic method. The method will thus be able to treat large and geometrically complex problems at a high level of accuracy (thanks to the Monte Carlo approach) in a reasonable computing time (thanks to the deterministic framework). Because Generation-IV systems have much more heterogeneous core geometries, the proposed technique is particularly well suited to such systems and is expected to contribute to a more faithful modelling of their behaviour. The project will thus consider the development of such a new hybrid method, its test on given reference problems and its optimization, prior to its application on large and complex situations representative of Generation-IV systems. Both steady-state and dynamical cases under stationary conditions will be considered.
Denna sidan finns endast på svenska
- Vetenskapsrådet (VR) (Offentlig, Sweden)