CTF
Subchannel Thermal-Hydraulics Code
Industry-standard tools for reactor thermal-hydraulics, neutronics,
and multi-physics analysis — developed at NC State University.
NEM
Nodal Expansion Method for Neutronics
Forum
Community Discussion & Support
Simulator
GenIV Reactor Simulators
OpenCTF-R
Open-Source Residual Solver
Information
Events, News & General Information
About the Reactor Dynamics and
Fuel Modeling Group
The Reactor Dynamics and Fuel Modeling Group (RDFMG), established at Penn State and now based at North Carolina State University, has established expertise in developing, validating, and applying methodologies in core neutronics, core and system thermal-hydraulics, and coupled neutronics/thermal-hydraulics/fuel performance calculations. Efforts have focused on development and application of calculation schemes for multi-physics, multi-scale simulations for advanced reactor design and safety analyses, supplemented by validation & verification and uncertainty quantification.