TY - JOUR
T1 - Narrow heat flux channels in the COMPASS limiter scrape-off layer
AU - Horacek, J.
AU - Vondracek, P.
AU - Panek, R.
AU - Dejarnac, R.
AU - Komm, M.
AU - Pitts, R. A.
AU - Kocan, M.
AU - Goldston, Robert James
AU - Stangeby, P. C.
AU - Gauthier, E.
AU - Hacek, P.
AU - Havlicek, J.
AU - Hron, M.
AU - Imrisek, M.
AU - Janky, F.
AU - Seidl, J.
N1 - Funding Information:
This work was supported by the projects GA CR P205/12/2327 and MSMT LM2011021. This project has received funding from the European Union’s Horizon 2020 research and innovation program under grant agreement number 633053. The views and opinions expressed herein do not necessarily reflect those of the ITER Organization and of the European Commission.
Publisher Copyright:
© 2014 Elsevier B.V.
PY - 2015/7/22
Y1 - 2015/7/22
N2 - Abstract The ITER first wall is designed for start-up and ramp-down in limiter configuration. The wall panels are toroidally shaped in order to spread the incident parallel power flux q|| uniformly, assuming a single decay length λq whose value is not known from first principles. In order to study the scaling of q|| with plasma parameters, infra-red viewing of specially-designed limiters has been used on the COMPASS tokamak in ∼100 discharges with scans in Ip, ne and for all combinations of magnetic field and Ip directions. The IR measurement clearly shows that in addition to the main SOL heat flux profile with λq > 40 mm, a steep gradient (λqnear = 4 ± 2 mm) dominates q|| near separatrix. This appears independently of limiter shaping, insertion with respect to neighbors and incident field-line angles. Good agreement is found between the measured λqnear and the prediction of a heuristic drift-based model.
AB - Abstract The ITER first wall is designed for start-up and ramp-down in limiter configuration. The wall panels are toroidally shaped in order to spread the incident parallel power flux q|| uniformly, assuming a single decay length λq whose value is not known from first principles. In order to study the scaling of q|| with plasma parameters, infra-red viewing of specially-designed limiters has been used on the COMPASS tokamak in ∼100 discharges with scans in Ip, ne and for all combinations of magnetic field and Ip directions. The IR measurement clearly shows that in addition to the main SOL heat flux profile with λq > 40 mm, a steep gradient (λqnear = 4 ± 2 mm) dominates q|| near separatrix. This appears independently of limiter shaping, insertion with respect to neighbors and incident field-line angles. Good agreement is found between the measured λqnear and the prediction of a heuristic drift-based model.
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U2 - 10.1016/j.jnucmat.2014.11.132
DO - 10.1016/j.jnucmat.2014.11.132
M3 - Article
AN - SCOPUS:84937731251
SN - 0022-3115
VL - 463
SP - 385
EP - 388
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 48728
ER -