A study of the annealing behavior of neutron irradiated graphite

摘要: Abstract Recycle is being considered as a waste mitigation option for irradiated graphite from gas cooled reactors. Thermal annealing was performed on samples to establish what fraction of in-crystal (displacement damage) and ex-crystal (pore generation) damage could be recovered. The sample dimensions electrical resistivity were measured after isochronal at 500, 1000, 1500, 2000 °C. Sample unaffected by annealing. Some the non-recoverable 2000 °C, this behavior which attributed (a) structural changes resulting pore generation (also causing annealing) or (b) defect structures in that persist even an temperature different low irradiation samples, T irr  > ∼400 °C, indicated established during these two regimes. Moreover, extent recovery much greater specimens with higher temperatures, small lower dose–low specimens. Evidently, some defects scatter trap electrons are still present crystal lattice their tenacity depends upon accumulated neutron dose.