NE 510
Nuclear Reactor Theory
University of New Mexico-Main Campus · UGRD · Fall 2026
1 section
Catalog description
Neutron transport equation, differential scattering cross section, diffusion approximation, one group diffusion theory including green s function and eigenfunction expansion, Breit-Wigner formula, slowing down theory, reactor kinetics, multigroup methods, topics selected from numerical methods for reactor analysis.
Sections
Current meeting, instructor, credit, and enrollment details
001
Availability not recently verifiedClass #new_mexico_main_campus-NE510Fall 2026UGRD3 credits
- Days & times
- No scheduled meeting time
- Meeting dates
- —
- Location
- —
- Instructor
- Staff
Class numbers and section codes come from the registrar.
Spot missing or incorrect course data?