High heat flux testing of first wall mock-ups with and without neutron irradiation

作者: G. Pintsuk , B. Bellin , A. Gervash , J. Linke , N. Litunovsky

DOI: 10.1016/J.NME.2016.02.003

关键词:

摘要: Abstract Beryllium as the plasma facing material for first wall of ITER will be exposed to thermal, particle and neutron loads. In frame European qualification program ITER, two HIPped beryllium small scale flat-tile mock-ups consisting a steel support structure, CuCrZr/Cu heat sink tiles on top were manufactured by CEA. One mock-up was irradiation up 0.75 dpa in RBT-6 fission reactor at Dimitrovgrad, Russia, while other one kept reference. Furthermore, an identical produced Russia manufacturing via electron beam induced rapid brazing also same conditions. For qualification, all three cyclic steady state loads facility JUDITH-1 maximum 3.0 MW/m2. Thereby, each tile loaded individually full loading area exceeds limits facility.

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