Nuclear thermal hydraulics
Module aims
This module provides a basic introduction to the thermal hydraulics of nuclear reactors, and associated issues in fluid mechanics.
Learning outcomes
On successfully completing this module, students will be able to:
- Explain the importance of thermal hydraulics and cooling in the context of nuclear reactors.
- Perform channel calculations of flow rate and temperature for nuclear reactors, and calculations of pin thermal performance.
- Explain the importance of critical heat flux and its physical manifestations understood, and its means of prediction
- Explain the role that buoyant flows can play in nuclear reactor cooling, and perform calculations involving this
Module content
- Within pin thermal analysis
- Within channel thermal analysis
- Buoyant flows in simple piping loops
- Numerical treatment of flows in one-dimensional piping loops
- The forms that critical heat flux can take, and the means of predicting it
- Concepts, terminology and calculations in two phase flow for nuclear power
Module lead
ECTS/FHEQ
5/7
Module code
MECH70001
Host department
Department of Mechanical Engineering
Term
Autumn
Time slot
AM
Teaching weeks
TBC
August resit opportunity?
Yes
How to apply
Via DSS
Application deadline
The third Friday of autumn term, 17.00
Places available (approximate)
10
Number of applicants (historic)
5
Criteria used for student selection
First come, first assigned a place if oversubscribed
Further information
Mechanical Engineering Undergraduate Office