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NUCLEAR REACTOR ANALYSIS

NE 505
Course 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.

Prerequisites

NE 405 , graduate/professional standing, or member of Engineering Guest Students

Satisfies

This course does not satisfy any prerequisites.

Credits

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Instructors (2026 Summr)

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