HTGR Knowledge Base
Conference Article: Graphite Materials Testing in the ATR for Lifetime management of Magnox Reactors
S. B. Grover, Idaho National Engineering and Environmental Laboratory, USA and M. P. Metcalfe, British Nuclear Fuels plc, Research and Technology, Berkeley Centre, United KingdomAbstract
A major feature of the Magnox gas cooled reactor design is the graphite core, which acts as the moderator but also provides the physical structure for fuel, control rods, instrumentation and coolant gas channels. The lifetime of a graphite core is dependent upon two principal aging processes: irradiation damage and radiolytic oxidation. Irradiation damage from fast neutrons creates lattice defects leading to changes in physical and mechanical properties and the accumulation of stresses. Radiolytic oxidation is caused by the reaction of oxidizing species from the carbon dioxide coolant gas with the graphite, these species being produced by gamma radiation. Radiolytic oxidation reduces the density and hence the moderating capability of the graphite, but also reduces strength affecting the integrity of core components. In order to manage continued operation over the planned lifetimes of their power stations, BNFL needed to extend their database of the effects of these two phenomena on their graphite cores through an irradiation experiment. This paper will discuss the background, purpose, and the processes taken and planned (i.e. post irradiation examination) to ensure meaningful data on the graphite core material is obtained from the irradiation experiment.
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key words: Gas Cooled Reactor, Nuclear Technology
- Reference:
- Proceedings of the Conference on High Temperature Reactors, Petten, NL, April 22-24, 2002
Organized by HTR-TN in cooperation with the European Nucler Society (ENS) and the IAEA- International Atomic Energy Agency, Vienna (Austria)
- HTR-2002, pp:1-7
- International Atomic Energy Agency, Vienna (Austria)