ORNL has a long history of reactor analysis using multigroup and continuous-energy physics with deterministic and Monte Carlo methods. The breadth of reactor neutronics includes:
- Multigroup cross section processing
- Neutron transport and diffusion
- Isotopic depletion, decay, and transmutation
These methods are regularly implemented in a wide variety of applications, including:
- Lattice physics for core analyses
- High-fidelity LWR core analyses
- Analysis and optimization of research reactors
- Optimization of advanced reactor designs and fuel cycle analyses
- Isotope production and material irradiation experiments in research reactors