Course Details in 2025/26 Session

Module Title	LM Radiation Transport and Reactor Kinetics
School	Metallurgy and Materials
Department	Metallurgy & Materials
Module Code	04 35121
Module Lead	Dr Sam Cruchley
Level	Masters Level
Credits	10
Semester	Semester 1
Pre-requisites
Co-requisites
Restrictions	None
Contact Hours	Lecture-20 hours Guided independent study-80 hours Total: 100 hours
Exclusions
Description	This module is designed to provide students with an understanding of the transport of radiation through materials, and methods of designing appropriate shielding for radiation facilities. The module also includes detailed coverage of neutron physics and thermodynamics within the reactor core, with theoretical methods of calculating important parameters used in reactor safety and control.
Learning Outcomes	By the end of the module students should be able to: Understand radiation transport in the context of a reactor and the solutions of the Boltzmann equation for different neutron sources ad boundary conditions. Understand the origin and role of delayed neutrons and the consequences for the build-up of reactor poisons. Be aware of methods of solving the Boltzmann Equation, including both Monte Carlo and deterministic methods
Assessment	35121-03 : Exam : Exam (Centrally Timetabled) - Written Unseen (100%)
Assessment Methods & Exceptions	Assessment: 3 hour written unseen examination (100%) Reassessment: Written examination
Other
Reading List