MSc Nuclear Science and Technology / Course details

Pre-course preparation will include:

Gamma radiation: Properties, interaction with matter (including biological effects), sources (types of), typical energies, X-sections

Neutron radiation: Properties, interaction with matter (including biological effects), sources (types of), typical energies (spectra), X-sections

Beta Radiation: Properties, interaction with matter (including biological effects and production of Bremsstrahlung), sources (types of), typical energies (spectra), X-sections

Radiation field quantities:  Flux, current, angular properties, vectors, distance fall-off

Direct-taught material will include:

•    Radiological Protection Principles

ICRP recommendations. Methods of dose control, limitation, ALARP. Current limits and constraints.

•    The Particle Transport Equation

Simple derivation, physical meaning of terms, simple solutions (exponential attenuation, infinite hydrogenous system)

•    An introduction to OpenMC & Validation

A description of the OpenMC code, how to use it and the choice of cross-section data.

•    Simple Shielding Methods

Hand calculations including Point sources, line sources, surface sources, infinite sources etc, solid angle fall-off. Attenuation curves, exponential attenuation, source strengths. Simple Codes, Point kernel, principles, limitations and buildup.

•    Monte Carlo Simulation

Review of methods available. Monte Carlo, deterministic.  Understanding of theory behind each. Particular issues with gammas and neutrons, secondary gammas etc. Advantages and disadvantages. Overview of underlying statistics, acceleration techniques, nuclear data, some classic examples illustrating strengths and weaknesses

•    Use of Monte Carlo Codes

Example codes e.g. MCBEND, OpenMC awareness of strengths and weaknesses.

•    Use of Deterministic Codes

1,2 and 3-D. Modelling techniques , nuclear data, some classic examples illustrating strengths and weaknesses. Attila, EVENT  

•    The shielding design process

Basics of designing shielding to achieve dose targets and to be ALARP

•    Applications of shielding codes

Illustration of shielding in real life. Concrete structures, penetrations, scatter…why ALARP etc.

Practical work in the Direct-taught week will include:

•    Validation of the OpenMC against an experimental neutron rig. The neutron and gamma field associated with rig will be simulated and experimentally validated.

•    2 experiments detailing:  

- The use of 3He gas detectors.  

- The shielding of an Am/Be neutron source.

The Post-course assignment will require students to either:

•    Utilise the code OpenMC to extend the in-course work to develop a computer model that produces a 5mm width collimated beam of thermal neutrons from a point isotropic Am/Be source of neutrons.  

Or

•    Design a new shielding rig capable of shielding a 1Ci Am/Be neutron source 

The unit aims to: introduce the subject of radiation shielding and illustrate solutions to the particle transport equation in the context of Monte Carlo and deterministic transport codes. Simple shielding methods will be compared with sophisticated complex calculations in order to familiarise students with the essential concepts. As well as the core material, the course has four external lecturers who are experts in their respective fields. The use of Monte Carlo and Deterministic Codes will be presented in the context of industry needs and requirements. Shielding applications and the shielding design process will be discussed. 

ILO 1

Understand the particle transport equation and the methodologies used to solve it.

ILO 2

Understand and be able to evaluate a shielding scenario using simple shielding methods (hand calculations).

ILO 3

Understand the concept of Monte Carlo and Deterministic methods and how they are applied to radiation shielding calculations

ILO 4

Understand the systematic process that must be followed to design shielding to adequately protect those working with ionising radiation.

ILO 5

Understand how the range of shielding solutions is consistent with common principles of radiation physics and radiological protection.

Short-course format:

Pre-course preparation: students provided with essential background material in electronic format (30 hours)

Direct-taught week includes 8 hours of lectures, 22 hours of practical laboratory work and 15 hours of tutorials and private study. (45 hours total)

Post-course assignment may apply the OpenMC programme to a specific task (75 hours) 

End of unit test - 16%

Practical work - 34%

Post-Course Assignment - 50%

Feedback provided with marked work after 2 weeks.

Radiation detection and measurement, G. Knoll