Nuclear Science and Technology

Core modules:

Nuclear Waste Immobilisation and Disposal

This course reviews basic approaches of nuclear waste management and gives an introduction of scientific fundamentals of nuclear waste processing and disposal. A range of topics will be considered including classification schemes, description of basic techniques of nuclear waste processing, methods of storage and disposal of different types of nuclear wastes. 

15 credits

Project

Students undertake a project on a topic agreed with their allocated academic supervisor; supervisor allocation takes into accounts students' specific interests. The project is an original research investigation carried out within a research group in the Department; to develop students' abilities to interact within a research group a defined piece of group work is undertaken early in the project. All projects include a literature survey involving students reading original papers and review articles from the scientific and technical literature. Most projects involve extensive laboratory work although some may be based primarily on a survey of the published literature or computational studies. The assessment of the project includes assessment of the group work, an interim report and final report along with a presentation on the work to staff and other students and an oral examination. Conduct throughout the project is also assessed.

60 credits

Optional modules - one or both from:

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

Radiation and Radiological Protection

Explains the properties of different types of radiation occurring as a result of nuclear processes and identifies means whereby levels of radiation and dosages can be detected and measured. The principles of radiation protection and shielding are outlined and demonstrated through practical experience with radioactive sources and detection equipment. The module concludes with an overview of ionising radiation regulations and legislation governing the impact of radiation on people and the environment. The safe handling of accidents is illustrated through case studies of real incidents.

On completion, students should have obtained:

A full understanding of the sources, types of radiation and hazards associated with nuclear processesKnowledge of radiation detection and monitoring equipmentAppreciation of the principles governing the design of radiological protection equipmentUnderstanding of Ionising Radiation Regulations

15 credits

Optional modules:

Reactor Physics, Criticality and 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

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

Decommissioning, Waste and Environmental Management

A suitable introduction to the basics of nuclear decommissioning, lower activity radioactive waste and environmental management for students with no experience of the nuclear industries in the U.K.

The module aims to introduce and develop subject knowledge and theoretical, conceptual and analytical skills in technical, environmental and policy issues and principles associated with nuclear decommissioning and waste management (principally lower activity wastes) and the environmental management thereof in the UK.

On completion, students should be able to:

Discuss the scientific, environmental and socio-political issues affecting the decommissioning
Acquire, evaluate and use the principal sources of data on issues affecting the decommissioning of nuclear facilities and nuclear waste management of nuclear facilities and legacy nuclear waste management
Critically evaluate decomissioning management.
Critically appraise the waste management principles applicable to nuclear decommissioning.

15 credits

Reactor Materials and Lifetime Behaviour

This module describes the science and engineering of reactor materials, and the factors that influence the lifetime of these materials, including corrosion, environmentally‐assisted fracture, and irradiation embrittlement. Other topics covered in this module include fracture mechanics and structural integrity, non‐destructive evaluation techniques, as well as plant monitoring and lifetime issues. Also considered are materials specifications and fabrication processes for materials used in nuclear power systems.

On completion, students should be able to:

Have an understanding/appreciation of the materials science structure/property relationships of key reactor materials, and how these are affected by corrosion and the environment (Light Water Reactors, AGRs).
An understanding of the methods of structural integrity assessment of reactor pressure vessels.
The ability to perform basic structural integrity assessment using the R6 code.
An appreciation of the methods of non‐destructive testing and plant monitoring with real-life examples.
An appreciation of the factors which limit the lifetime of reactor components, such as radiation damage and stress corrosion cracking.
An appreciation of the specifications and methods of material fabrication/joining for reliable performance in nuclear power system environments.

15 credits

Policy, Regulation and Licensing

The nuclear industry is one of the most heavily regulated industries in the UK. Regulatory issues necessarily impact upon the development of national policy in environmental and energy areas. This module covers the international and national legal frameworks for nuclear power and radioactive waste management including licensing issues covered by the Nuclear Installations Act, discharge authorisations under the Environmental Permitting (England and Wales) Regulations 2016 and planning for new build. The roles of the various regulatory bodies and other players are discussed. The module also addresses the role of the Nuclear Decommissioning Authority, decommissioning of nuclear facilities and UK radioactive waste management policies and national strategies. Students are introduced to basic legal principles as applied in the nuclear sector and are shown how to read case law and apply their knowledge to legal problems.

On completion, students should be able to:

explain the policy context in which the nuclear industry operates.
list key legal instruments and explain why they have been made.
explain the principles guiding regulation in the nuclear industry and comment on the way that they are used.
describe clearly the governing bodies, nationally and internationally, responsible for formulating policy, promulgating laws and regulations and enforcing them
explain clearly the responsibility of the employer and the individual in respect of ensuring nuclear safety.
identify the legislation applicable to the student's organisation, and how this is applied.

15 credits

Reactor Thermal Hydraulics

Fundamental to the design and safety of a nuclear reactor is the ability to remove energy safely from the core. This module therefore aims to describe the thermal hydraulic processes involved in the transfer of power from the core to the secondary systems of nuclear power plants. The principles of single phase and multiphase fluid dynamics and heat transfer will be studied and applied in the context of a range of different reactor types. The techniques developed will allow you to make assessments of various reactors against thermal limiting criteria.

On completion, students should have obtained:

An understanding of the heat transfer mechanisms in reactor systems
An understanding of fluid flow mechanisms in reactor systems
An appreciation of the limits on safe power removal from reactor cores
An appreciation of computer codes used to assess limiting power
An understanding of the influence of power conversion methods on reactor design.
The ability to perform basic calculations of thermal hydraulic quantities in core channels.

15 credits

Criticality Safety Management

This module provides a comprehensive introduction to nuclear criticality safety and the management of nuclear criticality safety in facilities, or situations, where fissile materials are encountered outside a nuclear reactor. It is designed to reflect the core competencies specified by the United Kingdom Working Party on Criticality (WPC), and consists of a basic nuclear reactor physics and fuel cycle pre-course reading component (mandatory for students who have not yet completed the N01 module) and a one-week taught component which includes a presentation from a visiting lecturer from industry/government, and an introduction to the use of Monte-Carlo codes for criticality safety analysis. The taught component is followed by a post-course criticality safety assessment that is designed to consolidate knowledge gained during the course and to enable students to join industry with a solid understanding of the criticality safety process.

On completion, students should be able to:

Perform a comprehensive criticality safety assessment of an operational or (hypothetical) planned facility or plant, or part therein, involved in the use, storage, or processing of fissile materials
Which will require them to:

Apply the appropriate regulatory legislation, guidance, or standards during this assessment

Apply the appropriate regulatory legislation, guidance, or standards during this assessment
Justify their analysis through the appropriate use of data, benchmarks, cross-comparison of methods, and/or sensitivity analysis.

15 credits

Management of the Decommissioning Process

Before nuclear decommissioning and radioactive waste management programmes of work are allowed to proceed, it is essential for clear and concise business cases to be made. This module sets out the framework for the management of the decommissioning process, developing the programme with plans, making the most appropriate use of available funds and other resources, and arrangements for managing, monitoring and controlling the work.

On completion, students should be able to:

Understand policy and business objectives of decommissioning
Carry out basic project financial and economic appraisals.
Understand the importance of hazard reduction, risk management, project prioritisation, and Tolerability of Risk (ALARP) arguments
Be conversant with modern project planning processes including Work Breakdown Structures, Organisational Breakdown Structures, , Activity Schedules, Cost Controls, and Critical Path Analysis
Understand Nuclear Safety Culture and Philosophy
Be knowledgeable of waste classification and characterisation approaches
Understand the documentation required to fulfill compliant and successful decommissioning processes.

15 credits

Experimental Reactor Physics

The module takes place in Vienna, Austria. The module consists of various experiments and hands-on training focused on the reactor and neutron physics, nuclear reactor dynamics, nuclear safety, and operation of nuclear reactor. The participants take active part in all experiments, and independently evaluate experimental data. The principles of neutron detection, the importance of delayed neutrons and their properties, the operating parameters of nuclear reactor, basic phenomena of reactor kinetics and dynamics are studied and demonstrated during various reactor experiments and measurements. Knowledge of the reactor I and C and safety aspects of nuclear reactor operation are gained during the hands-on reactor control

On completion, students should be able to:

Demonstrate a full understanding of the basic phenomena of reactor physics, behaviour of nuclear reactor and conditions for its safe operation.
Analyse and interpret data from reactor experiments and measurements.
Set-up neutron detection system and use it for an in-core reactor measurement.
Determine the delayed neutrons properties, their importance and utilize them for further measurements.
Measure and determine the neutron flux, control rod worth and reactivity by various methods.
Analyse and explain the reactor behaviour at various operating states and conditions and the reactor response to reactivity changes
Start-up and control zero-power reactor.
Evaluate the experimental results, prepare the lab protocols and present them.

15 credits

Severe Accidents

The ultimate safety objective of a nuclear power plant is to avoid the release of radioactive materials from the fuel of the core. For LWRs, the most likely cause of this is the loss of water from the core region, leading to a loss of suitable heat sink resulting in the eventual melting of the cladding and the collapse of the core. Modern nuclear power plants are designed so that the probability of radionuclide release occurring is very low, however should this event occur, the economic, environmental and health impacts are potentially so severe that the risk has elevated “nuclear severe accidents” as a scientific research field in its own right. Consequently, “nuclear severe accidents” has attracted billions of euros of research around the world over four decades, which has the attention of every nuclear regulator.

This module offers an introduction to nuclear severe accidents for LWRs by first introducing basic safety principles and the history of severe accidents. The module principally focuses on the various phenomena associated with the severe accident transient, covering the thermal-hydraulics of core uncovery through to the chemistry of radionuclides. The consequences of a severe accident are also covered, including the release of fission products into the environment and the emergency response. The module will also include an overview of some of the tools and codes available and widely used within the industry.

On completion, students should have obtained:

a recognition of the nuclear safety principles and how they apply to preventative and mitigative measures on a nuclear power plant;
an appreciation of the history of nuclear severe accidents and how that history has directed experimental research and plant design;
an appreciation of computer codes used to assess severe accident transients;
an understanding of the important severe accidents phenomena, from accident initiation to the eventual release of radionuclides;
an understanding of the societal impact of a severe accident.

15 credits