Engineering and the Environment, University of Southampton

Module overview

The aims of this module are to:

• Provide the students with an introduction to nuclear reactor technology with particular emphasis of power generation, hydrogen production, desalination and waste transmutation.
• Introduce the students to the key disciplines of reactor physics and thermal hydraulics as applied in the design of a nuclear reactor system for power generation, hydrogen production, desalination and waste transmutation.
• Introduce the students to the industry-standard codes used in the design process of nuclear reactors.

Objectives (planned learning outcomes)

Knowledge and Understanding:

• Describe the current status of nuclear reactors for electricity generation, powering of desalination and hydrogen production plants, marine power plants and special nuclear reactors for transmutation of nuclear waste.
• Appreciate the advantages and disadvantages of different types of nuclear reactor for applications in a sustainable energy economy.
• For the Pressurised Water Reactor (PWR) specifically, develop a detailed understanding of the underlying reactor physics and engineering aspects of the design, sufficient to predict the steady state and dynamic response of the plant.
• Understand the underlying principles of energy conversions systems for transforming nuclear heat into power and compare and contrast their applicability to electricity generation, powering of desalination and hydrogen production plants and special nuclear reactors for transmutation of nuclear waste.
• Identify the key safety issues associated with nuclear power generation.
• Demonstrate knowledge and understanding of the application of industry-standard design codes for nuclear reactors.
• Describe in outline the development of new-generation reactors and assess their application for electricity generation, powering of desalination and hydrogen production plants and special nuclear reactors for transmutation of nuclear waste.

Intellectual Skills:

• Apply the knowledge gained in the module to develop a mathematical model capable of predicting the steady-state and dynamic response of a nuclear power plants.
• Critically appraise different reactor types, including novel designs, for various applications in a sustainable energy economy.

Practical Skills:

• Using a 'basic principles' PWR simulator, operate a reactor during reactor start up, normal power operation, abnormal operations and shut down and explain the observed behaviour in terms of the underlying reactor physics and engineering.

Introduction: Historical development and current status of nuclear power programmes world-wide, covering present AGR, PWR, BWR, CANDU and fast reactors. Overview of the development, current status and future plans for 3rd generation reactors.

Basic Principles of Nuclear Reactors: Basic atomic and nuclear structure; Fission; The Fission Chain Reaction; Enrichment requirements and fuel types; Requirement for moderation and moderator types; Reactor design basics, including Fuel, Coolant, Moderator, Control Rods, Instrumentation, Reactor Pressure Vessel, Shielding, Containment, Heat removal systems, Primary and secondary systems, the Propulsion Train.

Reactor Types: Overview of PWR, BWR, CANDU, LMFBR, HTGR design principles; Dispersed, close coupled and integrated plants; Operating requirements and design criteria for various applications; Advantages and disadvantages of different reactor types for electricity generation, powering of desalination and hydrogen production plants and special nuclear reactors for transmutation of nuclear waste; Specific advantages of PWR for power and marine applications.

Nuclear Reactor Theory: Nuclear Reactions; Neutron reactions (scattering, absorption, fission); Cross sections and reaction rates; Typical neutron energy spectrum; Neutron cycle; Four-factor formula; Multiplication factor; Criticality and Reactivity concepts; Development of one-group diffusion equation; Ficks law; Materials and geometrical buckling; Development of the critical equation; Solutions of the diffusion equation for bare and reflected homogeneous reactors (slab, cylindrical, spherical); Limitations of one-group diffusion theory; Multi-group approaches.

Neutron Moderation: Requirement for neutron moderation; Coolant/moderator selection criteria; Slowing Down Theory; Slowing down length; Development of two-group diffusion equations; Solution of two-group diffusion equations; Flux profiles.

Reactor Heat Generation and Transfer from Fuel: Fission energy distribution; Radial and axial flux profiles; Power peaking factor; Volumetric thermal source strength; General thermodynamic considerations; Heat transfer processes from fuel to coolant, conduction, derivation of heat transfer equations and coefficients; Core thermal constraints; Radial and axial temperature profiles; Flux flattening techniques.

Primary Coolant System Design: Fluid flow; Frictional losses in pipes and channels; Pumped Flow; Thermodynamic considerations related to coolant circuit design; Heat exchanger types; Steam generators; Decay heat removal systems; Derivation of heat transfer equations for heat exchangers; Heat transfer coefficients; Single phase heat transfer; Two phase flow and heat transfer.

Propulsion System Design: Description of generic steam-based propulsion system (Engines, Condenser, Feed Water, Gearing, Shaft, Propeller); Efficiency calculations; Electric propulsion; Alternative energy conversion systems.

Reactor Kinetics: Prompt and delayed neutrons; Point kinetics equations; Sub-critical response and reactor start up; Zero energy reactor response to positive/negative reactivity additions, Prompt criticality.

Reactor Dynamics: System dynamic representation: zero-energy reactor, power reactor, coolant loops, steam generator and secondary systems; Reactivity coefficients; Whole plant dynamic response; Power reactor response to positive/negative reactivity additions; Power reactor response to load changes.

Reactor Instrumentation and Protection: Reactor protection system requirements; Instrumentation requirements; Neutron instrumentation; Operating principles of neutron detectors (fission chambers, BF-3 counters); In-core and ex-core neutron monitoring; Detector locations and implications for reactor power measurement; Non-neutron instrumentation (temperature, power, flow, etc); Typical reactor protection system.

The Shut Down Reactor: Fission products; Decay heat and decay heat removal systems; Grace time.

Through-life Effects: Fuel burn up; Conversion, breeding and fuel utilisation; Fission product poisoning; Long-term reactivity control; Core properties during lifetime; Refuelling.

PWR Simulator Session: Illustration of controlled reactor start-up, normal steady-state power operation, normal transient behaviour (load following, self-regulation), reactor protection system initiation; Reactor 'Scram' and fast recovery.

Overview of Modern Reactor Design Methods: Key issues in core design; Computer codes for reactor core design; Key issues in thermal hydraulic analysis; Computer codes thermal hydraulic analysis; Coupled reactor physics and thermal hydraulic codes; Introduction to acslXtreme™.

Future Reactor Development: New generation reactor development and possible applications for electricity generation, powering of desalination and hydrogen production plants and special nuclear reactors for transmutation of nuclear waste; Specific focus on Generation IV reactors and small reactors for various applications.

Teaching methods include:

• Lecture and tutorials (problem solving sessions)
• Practical demonstrations utilising a 'basic principles' PWR simulator

Learning activities include:

• Self learning by problem solving (tutorial problems and assignments)
• Utilisation of PWR simulator (group activities).

Students are provided with Lecture Notes (fully typed and illustrated) and copies of all presentational material used in lectures.

Recommended Text Books:

Introduction to Nuclear Engineering, J R Lamarsh (3rd Edition)

Feedback and Student Support During Study

• Tutor sessions, PWR simulator sessions and the coursework-based assignment provide means of monitoring student progress throughout the module.

Relationship between the teaching, learning and assessment methods and planned learning outcomes.

• The lectures, tutorial sessions, PWR simulator sessions and coursework-based assignments provide logical, coherent and integrated approach that should provide the student with a comprehensive introduction to nuclear and reactor physics.