Über die Autorin bzw. den Autor

Dr Gareth Neighbour completed his PhD in Materials Science at the University of Bath and joined AEA Technology at their Windscale plant from 1992 for four years where, amongst other things, he managed the integration of project safety, QA and engineering management systems. He then moved to University of Bath where he formed and then led the internationally recognised Bath Nuclear Materials Group. Dr Gareth Neighbour joined the University of Hull in February 2001 as a lecturer in Engineering. A significant proportion of his research is interdisciplinary in nature. His interest ranges from integrated management systems to fracture mechanics and fundamental structure-property relationships of engineering materials. With over 64 publications and a significant number of classified reports published by nuclear industry organisations, he is often invited to collaborate with national and international organisations and assist with organising conferences and committees.

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Gas-cooled, graphite-moderated nuclear reactors suffer ageing and degradation to the graphite during service posing a threat to the functionality of the core, and potentially, the safe operation of the reactor. Thus, the importance of modelling and measuring reactor core graphite properties and performance increases especially as continued use beyond the designed life time becomes significant. This book captures the proceedings from the third in a series of meetings addressing the extensive research and analysis performed to ensure the continuing safe performance of the graphite cores. Covering four broad themes: mechanistic; statistical; empirical; and, plant performance, this book should appeal to a broad range of readers from engineers and reactor operators to policy makers.

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Modelling and Measuring Reactor Core Graphite Properties and Performance

The Royal Society of Chemistry

Contents

Part A – Mechanistic, 
Towards a Structural Basis to the Physical Properties of Irraidated Polycrystalline Nuclear Graphite Brian Rand, 2, 
Property Changes of Polycrystalline Graphite due to Neutron Irradiation – A Critical Assessment after 70 Years of Research Gerd Haag, 9, 
Evaluation of Instantaneous Coefficient of Thermal Expansion of PGA Graphite Martin P. Metcalfe, Nassia Tzelepi and John F.B. Payne, 17, 
A Review of Current Finite Element Models for Irradiation Creep and Failure of Nuclear Graphite David W. J. Tanner, Adib A. Becker, Wei Sun and Tom H. Hyde, 23, 
Quasi-Brittle Fracture Concepts to Improve Structural Integrity Assessments of High Oxidation Weight Loss Graphite Components Andrew D. Hodgkins, Mahmoud Mostafavi, Peter E. J. Flewitt, Malcolm Wootton and Robert Moskovic, 31, 
Development of an Experimental and Simulation Process to Determine the End of Life Radionuclide Inventory of UK Irradiated Graphite Waste with a View to Long Term Disposal Greg Black, Abbie N. Jones and Barry Marsden, 39, 
The Oxidation of A3-3 Matrix Material in a CO2 Atmosphere in Support of a Nuclear Battery Type Reactor Design Joel Turner, Abbie N. Jones, Anthony J. Wickham, Marc Schmidt and Tim J. Abram, 44, 
Part B - Empirical, 
Theoretical Investigations into Sample Size Effects on Ultrasonic Measurements of Elastic Moduli John F.B. Payne and Nassia Tzelepi, 52, 
Mechanical Property Measurements on AGR Core Graphite Using Electronic Speckle Pattern Interferometry Paul Ramsay, 61, 
Quantitative Microstructure Characterisation of Advanced Carbons Using Image Analysis Theerapatt Manuwong, Gary D. Kipling, and Gareth B. Neighbour, 69, 
Revised Method For Graphite Weight Loss Prediction Jonathan E. Coote and Neil S. Headings, 76, 
On Large Scale Implicit Multibody Contact Dynamics Modeling with SOLFEC Tomasz Koziara and Nenad Bicanic, 84, 
Shaking Table Experimental Programme Luiza Dihoru, Adam Crewe, Colin Taylor and Tim Horgan, 91, 
A Novel Approach for Evaluating Surface Deposits on the Channel Wall Trepanned Graphite Samples Peter J. Heard, Malcolm R. Wootton and Peter E. J. Flewitt, 99, 
3H and 14C Release in UK Nuclear Graphite by Chemical Treatment Lorraine McDermott, Abbie N. Jones and Barry J. Marsden, 108, 
Part C – Statistical, 
Statistical Modelling of the Ageing of Graphite Cores Philip R. Maul, 116, 
Probability Modelling of Density Variability of Radiolytically Oxidised Graphite Robert Moskovic, 124, 
Statistical Analysis of Bore Cracking in AGRs Emma Tan, Kevin McNally and Nick Warren, 132, 
Statistical Modelling of Graphite Properties Peter C. Robinson and Philip R. Maul, 140, 
Part D - Plant, 
The Role of Data Visualisation in Core Inspection Decision Making Claire E. Watson, Peter C. Robinson and Philip R. Maul, 149, 
Non-Linear Seismic Assessment of AGRs: Incorporation of Aged Graphite Material Properties Kieran Scully and David Knowles, 158, 
Solid-Body Simulation of the Dynamic Response of an Array of Graphite Bricks Steve Brasier and Stuart Rogers, 166, 
Intelligent Graphite Core Condition Monitoring Christopher J. Wallace, Graeme M. West, Stephen D. J. McArthur and Michael Coghlan, 175, 
Decomposition of Refuelling Signals to Estimate Channel Bore Profiles Graeme M. West, Christopher J. Wallace, Stephen D. J. McArthur and Michael Coghlan, 183, 
The LEWIS Method for Channel Functionality Assessment Richard J. Crawford, 192, 
Part E – Open Discussion, 
Open Discussion Anthony J. Wickham, 202, 
Author Index, 212, 
Subject Index, 213,