| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 273481 | Fusion Engineering and Design | 2006 | 8 Pages |
Following the DEMO design analysis, two test blanket modules (TBM) were chosen in the RF for the development and testing in ITER: ceramic helium-cooled TBM and lithium self-cooled TBM. In the first one, lithium containing ceramics is used for tritium breeding, helium is used as a coolant and purge gas for tritium extraction, beryllium—as a multiplier. Ferritic steel is a structure material. In the second one lithium is used as tritium breeder and a coolant, and vanadium alloy of V–Cr–Ti system as a structure material.Conceptual designs of both TBMs and ancillary systems for their tests in ITER, strategy of tests, key R&D issues for both concepts are summarized. An international collaboration in R&D, development and testing of TBMs is of great importance due to shortage of testing space in ITER and due to high cost of the program.
