Über die Autorin bzw. den Autor

The Author Gareth Neighbour is a Senior Lecturer in Engineering at the University of Hull and is an accepted international authority on the phenomenon of irradiation creep in nuclear graphite. He has acted on various International Scientific Advisory Committees and was a member of the Organising Committee for the premier international carbon conference, Carbon 2006.

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Nuclear power currently contributes nearly a quarter of the electricity needs of the UK. Much of this is from nuclear reactor plants developed some fifty years ago. Consequently, in the next few decades, many of these reactors and components are coming to the end of their 'useful' life and strategies for the effective management of these decommissioned parts are paramount. Management of Ageing Processes in Graphite Reactor Cores discusses in detail both the scientific challenges and the issues involved in this subject. It begins with an introductory section on the fundamentals of reactor design and goes on to discuss graphite core behaviour under irradiation; graphite-component behaviour and its assessment; and whole core behaviour. The book concludes with a section on the lessons learned from decades of experience. Written by leading experts in the field, this high level book is ideal for both academia and industry, and would also be of relevance to policy makers and governments.

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Management of Ageing in Graphite Reactor Cores

The Royal Society of Chemistry

Contents

Part A – Designs & Operation, 
The Management of Magnox Graphite Reactor Cores to Underwrite Continued Safe Operation A T Ellis and K M Staples, 3, 
AGR Core Design, Operation and Safety Functions A G Steer, 11, 
An Overview of British Energy's Graphite Core Assessment Methodology M R Bradford, 19, 
UK Regulatory Strategy for Management of Graphite Ageing in Gas-Cooled, Graphite-Moderated Reactors G B Heys, 25, 
Part B – Advances in the Fundamental Knowledge of Graphite Behaviour under Irradiation, 
The Effects of Thermal Annealing on the Mechanical Properties of PGA Graphite M P Metcalfe and J F B Payne, 35, 
Development of a Model of Dimensional Change in AGR Graphites Irradiated in Inert Environments E D Eason, G N Hall and B J Marsden, 43, 
Relating Measurements of Mechanical Properties of Nuclear Graphites to Reactor Conditions. A Review of the Effects of Temperature and Pressure B McEnaney, 51, 
Flexural Strength of Graphite M Novovic, G B Heys and P Bowen, 59, 
Observations of Strain Localisation and Failure in Nuclear Graphite M R Joyce and T J Marrow, 67, 
Evaluation of the Brazilian Disc Test in Fracture Strength Measurements of Nuclear Graphite H Li, S L Fok and B J Marsden, 75, 
Irradiation Damage in Graphite from First Principles M Heggie, I Suarez-Martinez, G Savini, A El-Barbary, C Ewels and R Telling, 83, 
Development of a Code to Predict Fundamental Material and Fracture Properties of Nuclear Graphite C Lynch and G B Neighbour, 91, 
Modelling Graphite Ageing: Black Art or Forensic Science? M A Davies and M R Bradford, 100, 
A Holistic, Structurally- Based, Approach to Modelling Graphite Properties M R Bradford and A G Steer, 108, 
X-ray Tomographic Observations Applied to Porosity Models for the Thelmal Properties of Oxidised Nuclear Graphite L Babout, J Marrow, P Mummery and B J Marsden, 116, 
Part C - Advances in the Understanding of Graphite-Component Behaviour and its Assessment, 
Crack Propagation Resistance and Damage Mechanisms in Nuclear Graphite A Hodgkins, J Marrow, P Mummery, A Fok and B J Marsden, 127, 
Graphite Irradiation Testing at the NRG Petten J G van der Laan and J A Vreeling, 134, 
The Development of Measurement Techniques for Mechanical Properties Applicable to Small Reactor Graphite Samples N Tzelepi, M Brown, P C Matthews, J F B Payne and M P Metcalfe, 142, 
Techniques for Measuring the Properties of Unirradiated and Irradiated AGR Graphite S D Preston and W E Ellis, 150, 
Modelling of Nuclear Graphite under Irradiation Conditions D K L Tsang and B J Marsden, 158, 
Predicting the Stresses and Deformations of Irradiated Graphite Moderator Bricks C Jones, 167, 
Explicit Modelling of Graphite Core Components During a Reactor Thermal Transient C D Elcoate, G M Davis and J F B Payne, 175, 
Part D - The Consequences of Graphite Deterioration: Whole-Core Behaviour, 
PBMR Graphite Core Structures Fitness for Purpose Management Strategy M A Davies, M N Mitchell and P J Venter, 185, 
Seismic Modelling of an AGR Nuclear Reactor Core B Kralj, S Humphreys and B Duncan, 193, 
Measurement of AGR Graphite Fuel Brick Shri nkage and Channel Distortion A Cole-Baker and J Reed, 201, 
Investigation of Degradation of AGR Graphite Core Geometry Using a Whole Core Scale Model E Castro, 209, 
The Feasibility of Introducing Core Stiffening Devices and Diverse Shutdown Systems at Hinkley Point B / Hunterston B and Hartlepool / Heysham I M W Davies, 216, 
An Integrated Architecture for Graphite Core Data Analysis G Jahn, S McArthur and J Reed, 224, 
Graphite Core Condition Monitoring Through Intelligent Analysis of Fuel Grab Load Trace Data G M West, G J Jahn, S D J McArthur and J Reed, 232, 
Application of Whole Core Modelling Methodology to Life Extension of AGR Reactor Graphite Cores N McLachlan, D J Shaw and M H S Salih, 240, 
A Strategy for Monitoring Bore Cracking in AGR Graphite Cores P R Maul and P C Robinson, 248, 
Development and Validation of Whole Core Modelling Methodology for AGR Graphite Cores D J Shaw, M H S Salih and N Mclachlan, 256, 
Method for Determining if Control Rods and Fuel Stringer can be Inserted / Removed from an AGR Core A Thomson, M Ripley and N Mclachlan, 264, 
Part E - Lessons Learned from Management of Ageing Plant, 
Experience of Ageing Processes in Nuclear Power Reactors B Eyre, 273, 
The Importance of Understanding of Basic Principles in the Management of Ageing Plant M Burdekin, 282, 
An Overview and Summary of the Technical Papers in Parts B, C and D P E J Flewitt, B McEnaney, B J Marsden and G B Neighbour, 291, 
Author Index, 297, 
Subject Index (by Keywords), 298,