The [course_title] course teaches you the concepts and methods of transport theory needed in neutron science applications. You will know the effects of multiple interactions on neutron distributions and their applications to problems across the Nuclear Engineering department. Topics include Neutron fundamentals or Macroscopic Interactions, R-Matrix Theory, Neutron Thermalization, Detection and Data, Scattering Laws / SANS, Introduction to Monte Carlo, Photo transport or image rendering, Molecular Dynamics, etc.

Assessment

This course does not involve any written exams. Students need to answer 5 assignment questions to complete the course, the answers will be in the form of written work in pdf or word. Students can write the answers in their own time. Each answer needs to be 200 words (1 Page). Once the answers are submitted, the tutor will check and assess the work.

Certification

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Course Credit: MIT