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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

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Massachusetts Institute of Technology
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