TY - JOUR
T1 - Surface erosion issues and analysis for dissipative divertors
AU - Brooks, J. N.
AU - Ruzic, D. N.
AU - Hayden, D. B.
AU - Turkot, R. B.
N1 - Funding Information:
Work supported by the United States Department of Energy, Office of Fusion Energy.
PY - 1995
Y1 - 1995
N2 - Erosion/redeposition is examined for the sidewalls of a dissipative divertor using coupled impurity transport, charge exchange, and sputtering codes, applied to plasma solutions for the ITER design. A key issue for this regime is possible runaway self-sputtering, due to the effect of a low boundary density and nearly parallel field geometry on redeposition parameters. Net erosion rates, assuming finite self-sputtering, vary with wall location, boundary conditions, and plasma solution, and are roughly of the following order. 200–2000 Å/s for beryllium, 10–100 Å/s for vanadium, and 0.3–3 Å/s for tungsten.
AB - Erosion/redeposition is examined for the sidewalls of a dissipative divertor using coupled impurity transport, charge exchange, and sputtering codes, applied to plasma solutions for the ITER design. A key issue for this regime is possible runaway self-sputtering, due to the effect of a low boundary density and nearly parallel field geometry on redeposition parameters. Net erosion rates, assuming finite self-sputtering, vary with wall location, boundary conditions, and plasma solution, and are roughly of the following order. 200–2000 Å/s for beryllium, 10–100 Å/s for vanadium, and 0.3–3 Å/s for tungsten.
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U2 - 10.1016/0022-3115(94)00426-9
DO - 10.1016/0022-3115(94)00426-9
M3 - Article
AN - SCOPUS:0001023205
SN - 0022-3115
VL - 220-222
SP - 269
EP - 273
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
ER -