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Application of analytical and numerical techniques to neutron diffusion problems and point reactor kinetics. Includes data analysis; solution of ODEs and PDEs for nuclear criticality problems, and point kinetics with and without delayed neutrons.
Prerequisite: 231 and CS 151L and MATH **316.
Corequisite: 311.
Restriction: admitted to School of Engineering.
Principles of Nuclear Engineering - NE 231
Introduction to Transport Phenomena - NE 311
Applied Ordinary Differential Equations - MATH **316
MSC11 6325
1 University of New Mexico
Albuquerque, NM 87131
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