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Reactor Neutronics

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