Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
273448 | Fusion Engineering and Design | 2006 | 5 Pages |
Abstract
International thermonuclear experimental reactor (ITER) is anticipated as the only one step to DEMO fusion reactor. One of its main objectives is to demonstrate the availability and integration of technologies essential for a fusion reactor by testing of components for a future reactor including the test blanket modules (TBM) with different types of breeding materials.RF proposed to divide the TBM on two parts and to use two independent test blanket sub-modules (TBSM) which fixed on the frame in ITER horizontal experimental port for testing. CHC TBSM design description, its mechanical attachment on the frame, and principle schemes of helium cooling system and tritium cycle system are presented in this paper.
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Authors
V. Kovalenko, V. Kapyshev, A. Leshukov, V. Poliksha, G. Shatalov, Yu. Strebkov, A. Strizhov, M. Sviridenko,