1
This course is intended to introduce the student to the concepts and methods of transport theory needed in neutron science applications.
FREE
This course includes
Hours of videos
305 years, 6 months
Units & Quizzes
11
Unlimited Lifetime access
Access on mobile app
Certificate of Completion
This course is a foundational study of the effects of multiple interactions on neutron distributions and their applications to problems across the Nuclear Engineering department. Stochastic and deterministic simulation techniques will be introduced to the students.
Course Currilcum
- Macroscopic Interactions Unlimited
- Nuclear Data Unlimited
- R-Matrix Theory Unlimited
- Neutron Thermalization Unlimited
- Scattering Laws / SANS Unlimited
- Neutron Detection Unlimited
- Review of Probability and Statistics Unlimited
- Collision Physics and Sampling Unlimited
- Tallying and Uncertainties Unlimited
- Variance Reduction Techniques Unlimited
- Criticality Safety / Monte Carlo Criticality Unlimited
