MECH 420 - Nuclear Reactor Analysis

Institution:
The Citadel
Subject:
Description:
This course focuses on nuclear reactor systems, the release of nuclear energy in the reactor core, and its removal as heat for producing electric power. Specific topics emphasize reactor kinetics, heterogeneous reactors, control rods and shim, reactor poisons, heat transfer, and alternative energy systems. The fundamentals of transport theory and the solution to the transport equation using Monte Carlo N-Particle (MCNPX) transport code are introduced.
Credits:
3.00
Credit Hours:
Prerequisites:
Corequisites:
Exclusions:
Level:
Instructional Type:
Lecture
Notes:
Additional Information:
Historical Version(s):
Institution Website:
Phone Number:
(843) 225-3294
Regional Accreditation:
Southern Association of Colleges and Schools
Calendar System:
Semester

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