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Created by:
Last updated:
September 26, 2022
Duration:
Unlimited Duration
FREE
This course includes:
Unlimited Duration
Badge on Completion
Certificate of completion
Unlimited Duration
Description
This course is intended to introduce the student to the concepts and methods of transport theory needed in neutron science applications.
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 Curriculum
- 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
About the instructor
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Massachusetts Institute of Technology
