Nuclear Science and Technology

Example modules include:

Nuclear Waste Immobilisation and Disposal

This module considers fundamentals of nuclear waste management. A range of topics will be considered including contaminants and radiotoxicity, NORM, background radiation, risks, regulations, classification, origin and characteristics, short-lived and long-lived radionuclides, principles of waste management, characterisation, pre-treatment, thermochemical technologies, immobilisation by cements, bitumen and glass, vitrification technology, Joule heated ceramic and cold crucible induction melters, metal matrices, immobilising ceramics, glass ceramics and glass composite materials, self-sustaining immobilisation, performance of cementitious, bituminous, vitreous and metallic waste forms, radiation effects in glasses and ceramics, partitioning and transmutation, storage and disposal, safety assessment.

15 credits

Nuclear Fuel Cycle

To introduce and develop subject knowledge and theoretical, conceptual and analytical skills in the nuclear fuel cycle, which encompasses mining, fuel manufacture, reprocessing, storage and recycling or disposal.

On completion, students should be able to:

Explain the processes involved in the front- and back-ends of the once through fuel cycle
Critically review the advantages/disadvantages of fuel reprocessing with spent fuel management
Critically discuss the waste arising from each stage of the nuclear fuel including segregation and disposal.
Explore the challenges of emerging, competitive energy forms such as MOX, fast reactors and nuclear fusion.

15 credits

Reactor Physics, Criticality & Design

Nuclear reactors now account for a significant portion of the electrical power generated world-wide. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. Reactor physics is the core discipline of nuclear engineering and deals with the physical processes in reactors which are fundamental to the understanding of both operational and safety aspects of nuclear reactors. This module provides a historical background to reactor development, considers the range of possible designs, and explains the underlying nuclear physics principles and models that underpin an understanding of nuclear reactor operations.

On completion, students should be able to:

Compare and contrast the range of nuclear reactor designs, reactor codes, and transport/diffusion theory models used in the industry today.
Explain the physical principles which govern criticality, radioactive decay, reactor physics and kinetics, reactor system layout, and underlying nuclear processes which form the basis of how reactors work, run and are modeled in codes.
Derive expressions for criticality formulae, diffusion and transport equations for a variety of given situations and layouts.
Understand the importance of cross-sections, bucklings, delayed neutrons, six factor formula variables, the function of different parts of a nuclear reactor, and the crucial role played by neutronics in criticality and in the response of a multiplying system.
Know some background connected to the historical, environmental, and socio-political aspects of the nuclear industry, and issues related to later decommissioning.
Appreciate the need for knowledge of risk assessment, control, and safety for a reactor, and know about some of the consequences and issues connected with historical accidents.

15 credits

Radiation Shielding

This module gives an introduction to radiation shielding merging practical problems with industry standard transport codes in order to give a good understanding of the requirements for radiation shielding.

The aims of this module are:

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. Intensive training into the use of the Monte Carlo code MCNP will be provided.

On completion, students should have obtained:

Demonstrate an understanding of the Particle Transport equation and the transport codes and methodologies used to solve it.
Understand and be able to evaluate a shielding scenario using simple shielding methods.
Demonstrate an understanding of the Monte Carlo and Deterministic methods and they are applied to radiation shielding calculations.
Understand the systematic process that must be followed in order to design shielding to adequately protect those working with ionising radiation.
Have an understanding of how the range of shielding solutions is consistent with common principles of radiation physics and radiological protection.

15 credits