Neutron Interactions and Applications
Neutron transport theory gets a full graduate treatment in this MIT OpenCourseWare offering from the Nuclear Science and Engineering department. The course covers how neutrons scatter, absorb, and multiply as they move through matter, building the mathematical tools needed to model these distributions. Students work through both deterministic methods, such as solving the transport and diffusion equations, and stochastic simulation techniques like Monte Carlo methods used in reactor physics and radiation shielding problems. Materials include lecture notes, problem sets, and exams drawn from MIT's actual course offering, published under a Creative Commons license for self-study. The course assumes prior background in nuclear engineering and serves as a foundation for later coursework in reactor design, radiation detection, and other applications across the department. No instructor interaction or certificate is included, consistent with MIT OpenCourseWare's standard self-paced format.