Course Description and Goals:
This course familiarizes the student with current design practice and
regulation in the light water nuclear power reactor industry, which currently
produces 20 percent of the electricity used in the United States.
Thermal design for nuclear reactors is examined. This involves development
of one-dimensional two-phase flow models used in evaporators and steam
generators. Flow boiling heat transfer models are developed and thermal
limit models for steam generators and nuclear fuel assemblies are examined.
These combined skills allow the student to do first order thermal-hydraulic
design and analysis of a steam generator or nuclear fuel assembly.
Components, instrumentation and systems required for safe normal operation of a nuclear power reactor are reviewed. The function of components and systems employed for accident mitigation is also studied. Two-phase critical flow is examined and models for critical flow are used to evaluate liquid inventory loss rates for hypothetical pressure boundary failures. the relationship of these topics to current rules of the Nuclear Regulatory Commission is also presented.
Text: Nuclear Systems 1, Todreas and Kazimi, Taylor and Francis, 1993.
Student Effort Breakdown:
Homework Assignments, 25%
Review Activity
Written Report(s), 25%
Oral Report(s), 15%
In-Class Exams, 35%
Students in this Course will gain: