Abstract
The testing of breeding blanket concepts in ITER is recognized as an essential milestone in the development of a future reactor ensuring tritium self-sufficiency, extraction of high grade heat and electricity production. Europe is currently developing two reference breeding blankets for DEMO reactor specifications that will be tested in ITER under the form of test blanket modules (TBMs): the helium-cooled lithium-lead (HCLL) and the helium-cooled pebble-bed (HCPB) blanket concepts. Following the decision on ITER construction, the EU has reviewed and detailed the fundamental elements for implementing the future TBMs project aimed at delivering TBMs systems to ITER under suitable schedule and acceptance standards. The time schedule up to ITER operation being tight, the technical plan of the TBMs project over the next 10 years has been detailed.
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