MIT 22.01 Introduction to Nuclear Engineering and Ionizing Radiation, Fall 2016 - 21. Neutron Transport

MIT 22.01 Introduction to Nuclear Engineering and Ionizing Radiation, Fall 2016 Instructor: Michael Short View the complete course: https://ocw.mit.edu/22-01F16 YouTube Playlist: https://www.youtube.com/playlist?list=PLUl4u3cNGP61FVzAxBP09w2FMQgknTOqu The full, seven-dimensional neutron transport equation is developed from physical intuition, and putting that intuition into math. Aspects of neutron creation and transport are introduced as needed - neutron energy birth spectrum, flux, current, and many different types of neutron cross sections (fission, capture, scattering, total). It all comes down to balance - we equate the ways in which a control volume (like a reactor) can gain and lose neutrons of a certain energy, in a certain direction. License: Creative Commons BY-NC-SA More information at https://ocw.mit.edu/terms More courses at https://ocw.mit.edu