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N E 406: Nuclear Reactor Analysis

  • Catalog Description:
    The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.
  • Credits: 3
  • Prerequisites: NEEP 405
  • Official Course Description (pdf)

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