期刊
FUSION ENGINEERING AND DESIGN
卷 88, 期 9-10, 页码 1682-1685出版社
ELSEVIER SCIENCE SA
DOI: 10.1016/j.fusengdes.2013.03.021
关键词
ITER; Disruption; Massive gas injection; Numeric simulation; TOKES
Unmitigated disruptions in ITER can produce strong localized surface damage on the first wall (FW). Massive gas injection (MGI) systems are being designed to dissipate a large fraction of the plasma stored energy at the disruption thermal quench (TQ) and hence reduce the consequences for FW components. The stored energies can be high enough, however, for there to be potential for the photon flash at the MGI TQ to drive local melting of beryllium FW components. To estimate the poloidal distribution of FW surface temperatures, the MGI process is being simulated using the 20 code TOKES, assuming toroidal symmetry. High pressure neon injection, assimilation and transport of injected impurities through the entire plasma volume are modelled. The output of these simulations is used by the melt motion code MEMOS to assess the resulting maximum surface temperature and the regimes with melting on the FW surface. (C) 2013 Elsevier B.V. All rights reserved.
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