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This course is intended to introduce the student to the concepts and methods of transport theory needed in neutron science applications.
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English
English [CC]
FREE
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Description
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 content
- Neutron Fundamentals / Microscopic Interactions Unlimited
- 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
Instructor
Massachusetts Institute of Technology
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1916
1520
