Abstract
One of the basic purposes of the International Thermonuclear Experimental Reactor (ITER) programme is to test the elements of test blanket modules (TBMs) of the demonstration fusion reactor DEMO. In the present paper the opportunities for extrapolation of the test results of a Russian demonstration fusion reactor DEMO ceramic helium-cooled blanket TBM in the ITER to the DEMO blanket parameters are considered. A possible research and development plan for the Russian ceramic helium-cooled TBM, the types of TBM for testing in the ITER, and the TBM test plan are presented.
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