HIGH HEAT-FLUX TESTS OF MOCK-UPS FOR ITER DIVERTOR APPLICATION

One of the most difficult tasks in fusion reactor development is the d esigning, fabrication and high heat flux testing of actively cooled pl asma facing components (PFCs). At present, for the ITER divertor proje ct it is necessary to design and test components by using mock-ups whi ch reflect the real design and fabrication technology. The cause of fa ilure of the PFCs is likely to be through thermo-cycling of the surfac e with heat loads in the range 1-15 MW m(-2). Beryllium, tungsten and graphite are considered as the most suitable armour materials for the ITER divertor application. This work presents the results of the tests carried out with divertor mock-ups clad with beryllium and tungsten a rmour materials. The tests were carried out in an electron beam facili ty. The results of high heat flux screening tests and thermo-cycling t ests in the heat load range 1-9 MW m(-2) are presented along with the results of metallographic analysis carried out after the tests. (C) 19 98 Elsevier Science S.A. All rights reserved.