Fundamentals of nuclear reactors
(3 units)
Description: Nuclear physics, fission, and fusion; cross-sections; neutron flux and slowing-down; diffusion and transport; criticality condition and calculations; reactor kinetics and shielding; heat generation, transfer, and cooling; reactor materials; and reactor structure
Prerequisites: CHEM 0970 and PHYS 0175
It is recommended that students take the nuclear engineering courses in sequence for optimum learning.
Textbook: Nuclear Heat Transport, by M.M. El-Wakil, American Nuclear Society.
Course Objectives:
- Review basic theoretical concepts of nuclear physics, radioactivity, reactor physics, transmutation of nuclides, fuel depletion, and energy removal.
- Describe the interfaces between engineering disciplines involved with the design of a reactor core and the reactor coolant system for light water reactors.
- Describe the effects of energy generation and the temperature distributions in reactor elements and components.
- Discuss tasks of the reactor thermal designer, nuclear designer, and mechanical designer.
- Demonstrate fundamental calculational skills that aid in understanding the problems and solutions of reactor heat generation and energy removal systems.
- Discuss important social and technical issues related to nuclear science and technology.
Topics Covered:
- Examination of the design interfaces for the reactor core
- Review of reactor physics, reaction rates, and neutron flux distributions
- Reactor heat generation
- Heat conduction and removal in reactor fuel elements
- Nuclear, thermal, and mechanical design of a reactor core
- Radiation protection and shielding
- Reactor materials
- Reactor licensing and regulation
Class Schedule: One 150-minute period of lecture per week
Professional Component Contribution: Engineering science and design
Relationship to Program Objectives:
Prepared by: Larry Foulke
Date Prepared: August 15, 2006
