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The behavior of graphite under neutron irradiation

1986; American Institute of Physics; Volume: 4; Issue: 3 Linguagem: Inglês

10.1116/1.573432

1520-8559

B.T. Kelly,

Ion-surface interactions and analysis

The environment in which graphite is expected to be exposed in high power fusion reactors will impose a dose of ≂50 dpa, temperatures in the range 600–1200 °C, cyclic temperatures, and intense surface interaction with the plasma. A review is presented of the irradiation behavior of various types of graphite under these conditions, and we demonstrate that to have long life components it will probably be necessary to accept very large dimensional changes. The use of conventional graphites will give components of relatively short life due to the generation of porosity by internal strains. Consideration is given to the effects of helium generation in the lattice and surface erosion as contributory factors.