MIT 22.01 Introduction to Nuclear Engineering and Ionizing Radiation, Fall 2016
Instructor: Michael Short
View the complete course: ocw.mit.edu/22-01F16
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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.
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Негізгі бет 21. Neutron Transport
Пікірлер: 40