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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