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
Michael Bluck
ECTS/FHEQ
5/7
Module code
MECH70001
Host department
Department of Mechanical Engineering
Offered to
- Chemical Engineering
- Materials
Term
Autumn
Time slot
AM
Teaching weeks
2-11
August resit opportunity?
Yes
How to apply
Via www.imperial.ac.uk/dss once autumn term starts
Application deadline
24th October 2025
Places available (approximate)
10
Criteria used for student selection
N/A
Further information