The scaling of fuel recovered following un-mitigated disruptions in Alcator C-Mod with high-Z PFCs

B. Lipschultz, D.G. Whyte, R.S. Granetz, M.L. Reinke, S.M. Wolfe, A. Loarte

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The retention of fuel in plasma facing components (PFCs) is important for the viability of fusion - both in terms of economics and safety. This study shows that a single, un-mitigated, disruption can remove >30× more fuel than that retained in a single, 1s, C-Mod discharge with molybdenum and tungsten PFCs. The fuel is recovered due to heating of the near-surface (∼100 μm) during the thermal and current quench periods of the disruption. A regression analysis of full-current disruptions in a dataset of 3200 discharges leads to a scaling of fuel recovered approximately proportional to WTH1×WMAG2 where W and W are the thermal and poloidal magnetic energy inside the vessel respectively. Scaling by surface area and disruption time scales to ITER indicate 5-10 MA plasmas with low thermal energy (e.g. during current rampdown) may be ideal for removing fuel from plasma-wetted surfaces.
Original languageEnglish
JournalJournal of Nuclear Materials
Issue number1 SUPPL
Publication statusPublished - 1 Aug 2011

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