TY - JOUR
T1 - Ablation of fusion materials exposed to high heat flux in an electrothermal plasma discharge as a simulation for hard disruption
AU - Echols, J. R.
AU - Winfrey, A. L.
N1 - Funding Information:
Acknowledgments Work supported by Virginia Tech Nuclear Engineering Program. The authors would like to thank Dr. Mohamed Bourham for his useful discussions and guidance during this work.
PY - 2014/2
Y1 - 2014/2
N2 - Electrothermal plasma sources operating in the confined controlled arc discharge regime produce heat fluxes in the range expected for hard disruptions in future large tokamaks. The radiative heat flux produced inside of the capillary discharge channel is from the formed high density (10 23-1027/m3) plasma with heat fluxes of up to 125 GW/m2 over a period of 100 μs, making such sources excellent simulators for ablation studies of plasma-facing materials in tokamaks during hard disruptions. Graphite, beryllium, lithium, stainless steel, tungsten, copper, and molybdenum are among the materials proposed for use in fusion reactors. Computational experiments with the ETFLOW code using heat fluxes between 10 and 125 GW/m2 have shown low total erosion for the low-z materials Li, Be and C and higher erosion for high-z materials Fe, Cu, Mo and W. The time rate of material erosion for various ranges of heat fluxes shows increased erosion with time evolution over the 150 μs pulse length of the simulated disruption event. At the highest values of simulated heat flux, low-z materials were found to ablate almost identically. At all simulated values of heat flux, the ablation of high-z materials correlated positively with the z-number.
AB - Electrothermal plasma sources operating in the confined controlled arc discharge regime produce heat fluxes in the range expected for hard disruptions in future large tokamaks. The radiative heat flux produced inside of the capillary discharge channel is from the formed high density (10 23-1027/m3) plasma with heat fluxes of up to 125 GW/m2 over a period of 100 μs, making such sources excellent simulators for ablation studies of plasma-facing materials in tokamaks during hard disruptions. Graphite, beryllium, lithium, stainless steel, tungsten, copper, and molybdenum are among the materials proposed for use in fusion reactors. Computational experiments with the ETFLOW code using heat fluxes between 10 and 125 GW/m2 have shown low total erosion for the low-z materials Li, Be and C and higher erosion for high-z materials Fe, Cu, Mo and W. The time rate of material erosion for various ranges of heat fluxes shows increased erosion with time evolution over the 150 μs pulse length of the simulated disruption event. At the highest values of simulated heat flux, low-z materials were found to ablate almost identically. At all simulated values of heat flux, the ablation of high-z materials correlated positively with the z-number.
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U2 - 10.1007/s10894-013-9639-4
DO - 10.1007/s10894-013-9639-4
M3 - Article
AN - SCOPUS:84892669777
SN - 0164-0313
VL - 33
SP - 60
EP - 67
JO - Journal of Fusion Energy
JF - Journal of Fusion Energy
IS - 1
ER -