Astronuc said:I suspect there isn't any references. I do know that various groups are attempting to couple nuclear and T/H codes, and some perhaps have in a crude way.
Is this for an LWR system? PWR, BWR or both?
Will the code be used for steady-state or transient simulations?
The purpose of coupling between neutronic and thermalhydraulic codes is to create a more accurate and comprehensive simulation of nuclear reactor behavior. Neutronic codes simulate the neutron behavior in the reactor, while thermalhydraulic codes simulate the heat and fluid flow. By coupling these two codes, we can better understand the interaction between these two important aspects of nuclear reactor operation.
By coupling these two codes, we can more accurately predict the behavior of a nuclear reactor under various conditions and scenarios. This allows us to identify potential safety issues and make necessary changes to improve reactor safety. For example, coupling can help us understand how changes in the reactor's cooling system may affect the neutron behavior, and vice versa.
One major challenge is the different time scales at which neutrons and thermal fluids behave. Neutrons can move at the speed of light, while thermal fluids may take much longer to reach equilibrium. This requires careful consideration and adjustment of the coupling algorithms. Additionally, there may be differences in the spatial discretization and meshing between the two codes, which must be accounted for in the coupling process.
The information exchange between the two codes is typically done through a shared memory or a file interface. In a shared memory approach, the two codes run simultaneously and exchange data through a common data structure. In a file interface approach, the codes run separately and exchange data by reading and writing to a file. Both approaches have advantages and disadvantages, and the choice depends on the specific coupling methodology being used.
Coupling between neutronic and thermalhydraulic codes is commonly used in the design and analysis of nuclear reactors. It is particularly important in the design of advanced nuclear reactors, which may have complex geometries and operating conditions that require the coupling of these two aspects. It can also be used in research and development of new reactor technologies, as well as in safety studies and accident analysis.