ENME

ENME 431 - Nuclear Reactor Systems and Safety

3 Credits

Instructor 

Sanders, Robert

Textbook 

None required.  Course materials handed out in class and/or published on course ELMS site.

Prerequisites 

MATH 246
ENME 430

Description 

Engineering, material and thermal aspects of light water reactors, fast reactors, high temperature gas reactors, heavy water moderated reactors, breeder reactors, advanced reactors including GEN IV designs. Evolution of light water reactor safety and regulation in the US that has culminated in the current body of regulations.

Goals 

ENME 431 presents the major fluid systems used in nuclear reactor power plants, including the bases for the designs of these systems. The emphasis is on auxiliary and safety systems; however, primary coolant systems are also discussed. Systems used in existing nuclear power plants are presented, as well as proposed systems for advanced nuclear power plant concepts. Major components used in nuclear reactor fluid systems (pumps, valves and heat exchangers) are discussed. In addition, nuclear reactor safety, including regulatory requirements and safety analysis, are discussed. The major objective of ENME 431 is to have the student understand the fluid systems used in nuclear power plants, including the design bases and safety requirements. A student who successfully completes ENME 431 is able to demonstrate the ability to:
  • Understand the major fluid systems used in nuclear power plants.
  • Understand the design bases and safety requirements for the major fluid systems used in nuclear power plants.
  • Understand the design bases for major components used in nuclear power plant fluid systems including pumps, valves and heat exchangers.
  • Understand the regulatory and safety requirements for the major fluid system used in nuclear power plants.

Topics 

  • PWR and BWR power plant nuclear steam supply systems
  • Nuclear power plant safety systems
    • Components
    • Redundancy
    • Design bases
    • Safety analysis – system operations
  • Nuclear power plant auxiliary systems
  • Pumps, valves, heat exchangers
  • Safety systems and operation in advanced (next generation) nuclear power plants
  • USNRC regulatory requirements

Learning Outcomes 

  • an ability to design a system, component, or process to meet desired needs within realistic constraints such as economic, environmental, social, political, ethical, health and safety, manufacturability, and sustainability
  • an understanding of professional and ethical responsibility
  • the broad education necessary to understand the impact of engineering solutions in a global, economic, environmental, and societal context
  • a knowledge of contemporary issues

Class/Laboratory Schedule 

  • Two 75 minute lectures per week

Last Updated By 
Robert Sanders, June 2017