OSCAR system is used both as commercial industry support tool
The OSCAR system is used both as commercial industry support tool, as well as research vehicle in the area of nuclear reactor simulation and methods development. This diverse spread in application areas allows for numerous interesting projects which are presented at overview level on this page. Please contact us if you are interested to become involved in some of these activities, or have related projects that we could potentially collaborate on.

Research reactor operational support
The OSCAR code system is used as primary reactor calculational support system at various research reactors around the world. In particular, the SAFARI-1 reactor, operated by Necsa in South Africa, the HFR reactor operated by NRG in the Netherlands, the HOR reactor, operated by TU-Delft in the Netherlands and the MNR reactor, operated by McMaster University use OSCAR to support the daily operation of their reactors. Feasibility evaluations are ongoing with various other institutions, both for operating reactors as well as reactor concepts still in design phase.

Multi-physics, multi-fidelity, multi-code reactor modelling
The OSCAR system is designed to allow easy connection to both in-house and industry standard external code packages, for integrated use on a single, centralised reactor model, applicable to all codes. This unified approach allows seamless data exchange and input generation for physics and engineering solvers. The primary neutronic code system interfaced with OSCAR include the MGRAC nodal diffusion solver, the MCNP Monte Carlo code and the Serpent Monte Carlo code. Projects are currently ongoing with various partner institutions to couple codes such as RELAP, COBRA-TF and Flownex to the OSCAR system.

Benchmarking of advanced methods for reactor modelling
The development of new, state-of-the art modelling methods and approaches are a particular focus of the OSCAR development team. In particular, current focus areas include the development of novel solvers for neutron transport, spatially coupled neutronic thermal-hydraulic solvers, uncertainty propagation methods, as well as optimization and machine learning schemes. These new methods are continually benchmarked in ongoing international benchmarking projects, organized and co-funded by institutions such as the IAEA, OECD/NEA and EU. As example, some recent projects include an IAEA research reactor burnup benchmark, and EU Cortex project