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ENU 4103

Reactor Analysis and Computation I

University of Florida 4 credits Nuclear and Radiological Engineering

Course Description

Three one-hour lectures discussing neutron reactions, fission chain and criticality and neutron transport/diffusion for nuclear reactors. Neutron thermalization and thermal scattering kernels. Dynamic analysis of reactors including point and space-time models. Feedback and reactor dynamics and control. Short-term transient analysis and long-term time-dependence.

Code
ENU 4103
Credits
4
Subject
Nuclear and Radiological Engineering

Programs That Include This Course

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