Engineering Challenges Associated with the Life of Graphite Reactor Cores

Foreword — J. Reed
Preface and Acknowledgements — P. E. J. Flewitt, A. J. Wickham
Forward Strategy for Managing AGR Core Lifetime — J. Reed

ASSESSMENT
EDF Energy Creep Programme: Project ACCENT — M. Davies and others
Materials Test Reactor Programme for the Investigation of Graphite Irradiation Creep — T. van Staveren and others
Predictions of Average Weight Loss for the Active Core of Dungeness B — A. D. Moore and others
Measurement and Modelling of Void Structure and Diffusion Processes within Gilsocarbon Graphite — G. M. Laudone and others
Shaking Table Experiment for Graphite Core Lifetime Extension — T. Horgan and E. Webster
Future Methodologies for Seismic Assessment of AGR Graphite Cores — S. Brasier and others
Multi-Layer Array Rig Work for Seismic Behaviour with Cracked Bricks — L. Dihoru and others
Extension and Validation of the LEWIS Method for Channel Functionality Assessment — R. Crawford

ENGINEERING MODELS
The Benefits of Core Modelling in Underwriting Safe Reactor Operation — T. Bush
Statistical Analysis of AGR Graphite Core Reactor – Coupling Between a Statistical Analysis Tool (OPENTURNS) and a Nonlinear Dynamics Model (GCOEUR) – M. Berot and L. Pellet
Studies of the Material Properties of Nuclear Graphite Using the Random Finite Element Method — J. D. Arregui-Mena and others
Statistical Modelling of the Evolution of Graphite Properties and Reactor Cores — P. C. Robinson and others
On the Impact of Fast Neutrons on the Macroscopic Structure of Polycrystalline Graphite — G. Haag
Ongoing Development of Models to Predict AGR Core Component Condition — M. Joyce and others
A Micromechanistic Crystal Plasticity Model for Graphite — P. Yan and others
Modelling Single Axially-Cracked Bricks in the AGR Graphite Core: Model Development, Integrity Analysis, and Safety Implications — H. Teng and others
Towards a Notch-Sensitivity Strength Test for Irradiated Nuclear Graphite Structural Integrity — T. J. Marrow and others
An Overview of Cohesive Damage Models for Simulating Crack Growth Energy of Nuclear Graphite — S. T. Kyaw and others
Modelling Crack Propagation in Irradiated Graphite — P. Martinuzzi and others
Validation of Novel Finite Element Methods for Crack Propagation Studies in AGR Graphite Fuel Bricks — O. Booler and L. Kaczmarczyk
Measurement of Crack Front Profiles in Graphite and Comparisons with Novel Finite Element Predictions — P. Birkett and others

INSPECTION AND MONITORING
Reactor Inspection and Monitoring and its Role in the Reactor Safety Case — M. R. Bradford
Application of Optical Microscopy to Study Changes in Graphite Microstructure — M. P. Metcalfe and A. Tzelepi
Investigating the Effects of Stress on the Material Properties of Graphite Moderators using Confocal Laser Microscopy — J. E. L. Taylor and others
Automated Image Stitching for Inspection of Fuel Channels in AGR Reactor Cores — P. Murray and others
Non-Destructive Testing of AGR Graphite Cores — A. D. Fletcher and others
Development of New Techniques for AGR Graphite Post-Irradiation Examination — A. Tzelepi and P. Ramsay
Challenges Associated with Measuring the Mechanical Properties of Reactor Core Graphites for Input to Durability Models — D. Liu and others
Eddy Current Technique Development: Inspection Results from AGR Graphite Reactor Cores — M. Brown and others
Measuring the Poisson’s Ratio of AGR Graphite using the Time of Flight Method and Investigating Related Size Effects — S. Wilkinson and A. Tzelepi

DISCUSSION SESSIONS
Aligning the Modelling and Statistics with the Science — M. R. Bradford
Microstructural Modelling and Examination — T. J. Marrow and P. E. J. Flewitt
Relating Experiments to Core Modelling — N. McLachlan
The Best Use of Reactor Sampling and Inspection — J. Smith