RELAP-7 is a nuclear reactor system safety analysis code that is being developed at Idaho National Labs. It uses the same reactor kinetics model as the RELAP5 program. This model assumes nonlinear feedback from the moderator density and fuel temperature changes. It also assumes linear feedback from the moderator and fuel temperature changes. RELAP-7 uses a continuous finite element method with the MOOSE framework. In this model, a core channel represents the core thermal fluids, heat conduction, and conjugate heat transfer. The thermal and fluid analysis are 1-dimensional and the solid thermal analysis is two-dimensional. The time-dependent mass flow rates and volume components set the boundary conditions.
[[MOOSE Framework]]
[[Nuclear Thermal Rockets]] – used a RELAP-7 model to model a CERMET NTP with 250 MW power.
zhangPOINTKINETICSCALCULATIONS2013