Thermal-hydraulics and neutronic code coupling for RELAP/SCDAPSIM/MOD4.0


Akbas S., Martinez-Quiroga V., Aydogan F., Allison C., Ougouag A. M.

NUCLEAR ENGINEERING AND DESIGN, vol.344, pp.174-182, 2019 (SCI-Expanded) identifier identifier

Abstract

The design and analysis of energy systems requires robust and reliable computer codes that produce realistic results. The governing equations and closure models must represent the physical behaviors of the energy systems. Nuclear power plants, as the quintessential example of complex energy systems, must be modeled with such high-fidelity and accurate nuclear system codes in which thermal-hydraulics, neutronics and fuel performance models must be coupled for in order to produce high-fidelity predictions. Most commonly, the interplay between the various subsystems of a nuclear power plant (nuclear fuel, fluids, neutronics, control rods, power conversion, etc.) is modeled through a combination of different codes that are externally coupled.