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Heat Shock Tests on Beryllium Samples Before and After Neutron Irradiation

A. Lodato, M. Rödig, R. Duwe, H. Derz, J. Linke, R. Castro, A. Gervash

Fusion Science and Technology / Volume 38 / Number 3 / November 2000 / Pages 334-337

Technical Paper / Special Issue on Beryllium Technology for Fusion

Beside carbon materials and tungsten, beryllium will play an important role as plasma facing material (PFM) in the International Thermonuclear Experimental Reactor (ITER). It will mainly be used for the primary wall, the limiter and the upper baffle. During off normal operation the surface of Be may be loaded by severe thermal shocks, caused by plasma disruptions with energies of several ten MJ/m2 within tens of milliseconds. The influence of high heat fluxes on several un-irradiated Be grade have been investigated before. During the operation of ITER the material will suffer irradiation with 14 MeV neutrons generated in the fusion process. In order to study the material degradation caused by fast neutrons, different samples have been neutron irradiated in the High Flux Reactor (HFR) at Petten. The thermal shock behaviour of the different beryllium grade before and after neutron irradiation is now compared.

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