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:

  1. Explain the importance of thermal hydraulics and cooling in the context of nuclear reactors.
  2. Perform channel calculations of flow rate and temperature for nuclear reactors, and calculations of pin thermal performance.
  3. Explain the importance of critical heat flux and its physical manifestations understood, and its means of prediction
  4. 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

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

meugo@imperial.ac.uk

 

 

reverse