NUCLEAR REACTOR ANALYSIS
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 & course information
Requisites: N E 405 , graduate/professional standing, or member of Engineering Guest Students Course Designation: Grad 50% - Counts toward 50% graduate coursework requirement Repeatable for Credit: No Last Taught: Fall 2025 Learning Outcomes: 1. Analyze the performance of a nuclear fuel assembly throughout its lifetime Audience: Both Grad & Undergrad 2. Explain and demonstrate the changes in nuclear fuel assembly performance as operational parameters vary Audience: Both Grad & Undergrad 3. Use an industry-relevant software package to perform lattice calculations for analysis and design of a nuclear fuel assembly Audience: Both Grad & Undergrad 4. Explain and demonstrate the changes in nuclear fuel assembly performance as design parameters vary Audience: Both Grad & Undergrad 5. Compare different forms of analysis for the same application Audience: Graduate Learning Outcomes: 1. Analyze the performance of a nuclear fuel assembly throughout its lifetime Audience: Both Grad & Undergrad 2. Explain and demonstrate the changes in nuclear fuel assembly performance as operational parameters vary Audience: Both Grad & Undergrad 3. Use an industry-relevant software package to perform lattice calculations for analysis and design of a nuclear fuel assembly Audience: Both Grad & Undergrad 4. Explain and demonstrate the changes in nuclear fuel assembly performance as design parameters vary Audience: Both Grad & Undergrad 5. Compare different forms of analysis for the same application Audience: Graduate
Sources
- Course catalogue ↗2026-2027