Engineering of Nuclear Reactors
Engineering of Nuclear Reactors
As taught in: Fall 2007
The Supercritical-Water-Cooled Reactor (SCWR) system is a high-temperature, high-pressure water cooled reactor that operates above the thermodynamic critical point of water. The SCWR system is primarily designed for efficient electricity production. (Image courtesy of the Idaho National Laboratory.)
Course Features
Course Description
This course covers the engineering principles of nuclear reactors, emphasizing power reactors. Specific topics include power plant thermodynamics, reactor heat generation and removal (single-phase as well as two-phase coolant flow and heat transfer), and structural mechanics. It also discusses engineering considerations in reactor design.
Course Objective
To understand and model the thermal-hydraulic and mechanical phenomena key to the effective, reliable and safe design and operation of nuclear systems.
Course Summary
- Introduction to nuclear power systems
- Thermal-hydraulics:
- Thermal parameters: definitions and uses
- Sources and distribution of thermal loads in nuclear power reactors
- Conservation equations and their applications to nuclear power systems: power conversion cycles, containment analysis
- Thermal analysis of nuclear fuel
- Single-phase flow and heat transfer
- Two-phase flow and heat transfer
- Structural mechanics:
- Fundamentals of structural mechanics
- Applications to nuclear systems
Texts
Todreas, Neil E., and Mujid S. Kazimi. Nuclear Systems: Thermal Hydraulic Fundamentals. Vol. 1. New York, NY: Taylor & Francis Inc., December 1, 1989, 3rd printing. ISBN: 9781560320517.MIT Notes on Structural Mechanics.
No comments:
Post a Comment