User Group Meetings

RDFMG hosts annual user group meetings for CTF and related codes. These meetings are typically held in conjunction with the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) benchmark workshops organized by the OECD/NEA. The meetings provide a platform for users to share their experiences, present new developments, and discuss best practices.

Meeting topics typically include:

  • Code development progress and new features
  • Verification and validation results
  • Multi-physics coupling methodologies
  • Uncertainty quantification studies
  • Industrial and academic applications
  • Training sessions for new users
Reactor thermal-hydraulics research

Thermal-Hydraulics

Advanced subchannel and system-level thermal-hydraulic analysis for light water reactors and advanced reactor designs, including PWR, BWR, VVER, SMR, and Generation IV concepts.

Neutronics calculation and reactor physics

Neutronics

Core neutronics analysis using the Nodal Expansion Method for efficient solution of multigroup neutron diffusion equations, enabling accurate power distribution predictions.

Multi-physics coupling in reactor simulation

Multi-Physics Coupling

Development of coupled neutronics/thermal-hydraulics/fuel performance calculation schemes for multi-physics, multi-scale simulations supporting advanced reactor design and safety analysis.

Join the RDFMG Community

Whether you're a researcher, student, or industry professional, we welcome your participation. Join the user group, contribute to code development, or collaborate on research projects.

Contact the RDFMG Team

Questions about events, research, or collaboration opportunities?

Phone

919-515-2301

Address

Reactor Dynamics and Fuel Modeling Group
Department of Nuclear Engineering
North Carolina State University
3140 Burlington Engineering Labs
2500 Stinson Drive
Raleigh, NC, USA 27695-7909