The Chair has been active in the field of computational reactor physics for more than 10 years. The Chair supports the Nuclear
Analysis Group (GAN), which is specialized in neutron transport, including the development of new numerical methods in
transport and diffusion theory (collision, probability methods, method of characteristics, finite elements, Pn and Bn methods,
generalized perturbation theory, nodal methods).
The major products of the research group are the DRAGON code, a multigroup neutron transport code for the analysis of 2D and 3D
assemblies with complex geometries, as well as the TRIVAC diffusion module for reactor design, simulation and fuel management
calculations. A major application of these codes is the OPTEX procedure for CANDU fuel management optimization using
Generalized Perturbation Theory (GPT).
Research Personnel
Professors/Researchers: 2
Graduate Students: 5
Postdoctoral Fellows: 1
Research Assistants and Technicians: 2
Specialized Equipments
Computers, workstations.
External Sources of Funding
Hydro-Québec, Atomic Energy of Canada Ltd, CANDU Owner's Group (COG).
