Abstract: The ITER TBM Program, where TBM stands for Test Blanket Module, is a specific research activity within ITER, involving all ITER Members. It is foreseen to install a number of four different Test Blanket Systems, representative for tritium breeding concepts of the concerned ITER members and operate them simultaneously. An overview of the TBM program in ITER, its testing objectives, and its current status will be provided.
Three systems use ternary oxide lithium compounds as solid breeder, and beryllium as neutron multiplier, and one employs lithium-lead eutectic alloy in a loop. The applied coolants are high pressure water (600 K) or helium (up to 773 K). The structural material for the TBMs are so-called reduced-activation ferritic-martensitic steels, specially developed for the fusion life cycle.
The tritium as produced by the fusion neutrons is on-line extracted from the breeding zone or from the lithium-lead loop. This tritium extraction system is housed in of the rooms of the ITER tritium plant, and there it allows a batch-wise transfer to the tokamak exhaust system. It is foreseen to have the TBMs exchanged with different versions and have the irradiated part exported to hot cell facilities of the ITER members for post-test examinations. Some elements of the new TBM research plan will be discussed.
Note: this seminar is exceptionally on a Friday
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