ACCURATE FUEL BEHAVIOR PREDICTIONS
PEGASUS has a unique 2D/3D finite element engine coupled with a superior thermo-mechanical contact algorithm
Solve the Most Challenging Nuclear Fuel Problems – Optimize Fuel Performance
PEGASUS is a next generation nuclear fuel behavior code capable of analyzing steady state and transient fuel rod response for conventional and accident tolerant LWR fuel as well as advanced reactor TRISO fuel.
The code is a culmination of over four decades of advanced nuclear fuel behavior knowledge and experience. It will model fuel rod behavior for the entire fuel cycle from startup, operation, reactor transients, and ultimately through spent fuel transportation and permanent storage.
APPLICATIONS
SPECIALIZED ANALYSIS
LWR startup, operational, and specialized analyses such as 2D/3D pellet-cladding interaction (PCI), missing pellet surface (MPS), and fuel rod failure margin analyses
3D MPS Rod Segment Model | 2D R-θ MPS Model
ADVANCED FUEL
Application for advanced fuel systems such as TRISO-based designs for gas-cooled and other advanced reactor systems
3D TRISO Fuel Kernel Model Geometry
SPENT FUEL
Uniquely capable of spent fuel assessment and integrity analyses supporting testing, transportation, and storage, based on the combination of nuclear fuel performance and structural analysis modeling capability
Spent Fuel Rod Bend Test Simulation
RELATED MATERIALS