NE 405:  Reactor Dynamics, Control and Safety (Old)

The following topics are discussed during the semester.  Students work in small study groups and discuss reactor safety issues and events.

1. Introduction
• Nuclear plant systems in pressurized water reactors (PWRs) and boiling water reactors (BWRs).
• Plant control and safety systems.
• Course overview and expectations.
2. Reactor Kinetics
• Development of point reactor kinetics equations.
• Subcritical reactor.
• Power reactor and feedback effects.
3. Reactor Core Heat Transfer
• Nodal model of a PWR core dynamics.
• Transient analysis.
• Linearized equations and frequency response analysis.
4. Primary and Secondary Systems in a PWR Plant
• Pressurizer.
• U-tube and once-through steam generators.
• Feedwater heaters.
• Emergency core cooling system.
• Residual heat removal system.
• Chemical and volume control system.
5. Control Systems in a PWR
• Reactor power controller (Tavg control).
• Pressurizer pressure controller.
• Three-element steam generator level controller in a U-tube steam generator.
6. Reactor Safety Systems
• Defense-in-depth design.
• Safety systems.
• Review of nuclear plant safety-related events.
7. Student Presentations

Reactor Dynamics, Control and Safety
 
 

TOPIC	Class Periods (1 period=50 min)
Introduction to reactor dynamics, control and safety.  Nuclear plant systems in PWRs and BWRs.  Course overview and expectations.	2
Nuclear reactor kinetics.  Subcritical reactor.  Power reactor and feedback effects.	4
Reactor core heat transfer model.  Transient analysis.  Linearized system response.	4
Primary and secondary systems in a PWR plant and their dynamic modeling.	8
Control systems in a PWR.	2
Reactor safety systems.	4
Presentations by students on reactor safety-related events, and reactor design and regulatory issues.	16

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