NEEP 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 or Corequisites: NEEP 405
• Official Course Description (pdf)

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• Past Semester Courses

Fall 2011 (1122)

NE 406 Nuclear Reactor Analysis Fall 2011 (1) Sections: 001

Fall 2009 (1102)

NE 406 Nuclear Reactor Analysis, Fall 09 Sections: 001