Management of Ageing in Graphite Reactor CoresGareth B. Neighbour The Special Publications Series is a collection of books produced from the proceedings of international symposia. Editors bring together contributions from authorities in the field and the books provide snapshots of the latest developments of that field. |
Contents
The Management of Magnox Graphite Reactor Cores to Underwrite Continued | 3 |
AGR Core Design Operation and Safety Functions | 11 |
An Overview of British Energys Graphite Core Assessment Methodology | 19 |
UK Regulatory Strategy for Management of Graphite Ageing in GasCooled | 25 |
Part B Advances in the Fundamental Knowledge of Graphite Behaviour | 33 |
Development of a Model of Dimensional Change in AGR Graphites Irradiated in | 43 |
Relating Measurements of Mechanical Properties of Nuclear Graphites to Reactor | 51 |
Flexural Strength of Graphite | 59 |
Observations of Strain Localisation and Failure in Nuclear Graphite | 67 |
Evaluation of the Brazilian Disc Test in Fracture Strength Measurements of | 75 |
Irradiation Damage in Graphite from First Principles | 83 |
Development of a Code to Predict Fundamental Material and Fracture Properties | 91 |
of Nuclear Graphite | 158 |
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Common terms and phrases
Advanced Gas-cooled Reactors agent AGR core AGR graphite core AGR reactor ALARP AMEC analysis assessment brick cracking British Energy British Nuclear Group calculations control rods core behaviour core components core distortion core modelling methodology creep degradation developed dimensional change disc dose doubly cracked bricks effects Email event failure fast neutron FGLT data Figure finite element fracture fuel bricks fuel channel Gas-cooled Reactors geometry graphite bricks graphite components graphite core safety graphite reactor cores GTAC High Flux Reactor initial inspection interactions irradiated graphite irradiation keyway Keywords ligament Magnox Magnox reactors management of ageing material properties measurements methods microstructure multi-agent system normal operation nuclear graphite paper parameters PBMR plant potential predictions programme radiolytic oxidation refuelling significant specimens station strain strategy strength techniques temperature tensile tensile stress Test Reactor thermal expansion thermal stresses trepanned understanding validation weight loss whole core modelling Young's modulus