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 |
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Common terms and phrases
1/8th scale Advanced Gas-cooled Reactors AGR core AGRIGID analysis annealing assessment behaviour bore brick cracking British Energy British Nuclear Group calculated CBMU compressive control rods core distortion core modelling methodology creep strain developed diameter dimensional change disc displacements dose doubly cracked bricks effects elastic Energy Generation Ltd failure fast neutron FE model FGLT data finite element fracture fuel channels geometry graphite bricks graphite components GTAC Hinkley Point initial inspection interaction interstitial bricks irradiation keyway layer load Magnox material properties maximum measured mechanical method microstructure monitoring multi-agent system neutron irradiation nuclear graphite operation paper parameters PBMR plant Poisson's ratio pore porosity predictions programme radiolytic oxidation reactor core refuelling samples scale core rig Shape Amplitude shown in Figure shrinkage shutdown specimens strength stress structure TAGSI temperature tensile thermal annealing trepanned validation weight loss whole core modelling Young's modulus