dc.creator | Horacek, J. | es |
dc.creator | Pitts, R.A. | es |
dc.creator | Adamek, J. | es |
dc.creator | Arnoux, G. | es |
dc.creator | Bak, J.G. | es |
dc.creator | Jet Contributors | es |
dc.creator | García Muñoz, Manuel | es |
dc.date.accessioned | 2020-08-27T14:44:18Z | |
dc.date.available | 2020-08-27T14:44:18Z | |
dc.date.issued | 2016-07 | |
dc.identifier.citation | Horacek, J., Pitts, R.A., Adamek, J., Arnoux, G., Bak, J.G., Jet Contributors, y García Muñoz, M. (2016). Multi-machine scaling of the main SOL parallel heat flux width in tokamak limiter plasmas. Contributions to Plasma Physics, 58 (7), 074005-. | |
dc.identifier.issn | 0741-3335 | es |
dc.identifier.uri | https://hdl.handle.net/11441/100501 | |
dc.description.abstract | As in many of today’s tokamaks, plasma start-up in ITER will be performed in limiter
configuration on either the inner or outer midplane first wall (FW). The massive, beryllium
armored ITER FW panels are toroidally shaped to protect panel-to-panel misalignments,
increasing the deposited power flux density compared with a purely cylindrical surface.
The chosen shaping should thus be optimized for a given radial profile of parallel heat flux,
q in the scrape-off layer (SOL) to ensure optimal power spreading. For plasmas limited
on the outer wall in tokamaks, this profile is commonly observed to decay exponentially
as q q = − exp ( / r λ ) 0 q omp , or, for inner wall limiter plasmas with the double exponential
decay comprising a sharp near-SOL feature and a broader main SOL width, λq
omp. The initial choice of λq
omp
, which is critical in ensuring that current ramp-up or down will be
possible as planned in the ITER scenario design, was made on the basis of an extremely
restricted L-mode divertor dataset, using infra-red thermography measurements on the
outer divertor target to extrapolate to a heat flux width at the main plasma midplane. This
unsatisfactory situation has now been significantly improved by a dedicated multi-machine
ohmic and L-mode limiter plasma study, conducted under the auspices of the International
Tokamak Physics Activity, involving 11 tokamaks covering a wide parameter range with
R = = 0.4–2.8 m, 1 B I 0 p .2–7.5 T, = 9–2500 kA. Measurements of λq
omp
in the database
are made exclusively on all devices using a variety of fast reciprocating Langmuir probes
entering the plasma at a variety of poloidal locations, but with the majority being on the
low field side. Statistical analysis of the database reveals nine reasonable engineering
and dimensionless scalings. All yield, however, similar predicted values of λq
omp
mapped
to the outside midplane. The engineering scaling with the highest statistical significance,
λ = ( / ( )) ( / /κ) − −
q 10 P V W m a R omp tot 3 0.38 1.3
, dependent on input power density, aspect ratio and elongation, yields λq omp = [7, 4, 5] cm for Ip = [2.5, 5.0, 7.5] MA, the three reference limiter plasma currents specified in the ITER heat and nuclear load specifications. Mapped to the inboard midplane, the worst case (7.5 MA) corresponds to λq ~ 57 1 ± 4 imp mm, thus consolidating the 50mm width used to optimize the FW panel toroidal shape. | es |
dc.description.sponsorship | EURATOM 633053 | es |
dc.description.sponsorship | Czech Science Foundation GA CR P205/12/2327, GA15-10723S, MSMT LM2011021 | es |
dc.description.sponsorship | US Department of Energy DE-FG02- 07ER54917, DE-AC02-09CH11466, DE-FC02-04ER54698 | es |
dc.format | application/pdf | es |
dc.format.extent | 12 p. | es |
dc.language.iso | eng | es |
dc.publisher | IOP Publishing | es |
dc.relation.ispartof | Contributions to Plasma Physics, 58 (7), 074005-. | |
dc.rights | Attribution-NonCommercial-NoDerivatives 4.0 Internacional | * |
dc.rights.uri | http://creativecommons.org/licenses/by-nc-nd/4.0/ | * |
dc.subject | Tokamak | es |
dc.subject | ITER | es |
dc.subject | SOL decay length | es |
dc.subject | SOL width | es |
dc.subject | Scaling | es |
dc.title | Multi-machine scaling of the main SOL parallel heat flux width in tokamak limiter plasmas | es |
dc.type | info:eu-repo/semantics/article | es |
dcterms.identifier | https://ror.org/03yxnpp24 | |
dc.type.version | info:eu-repo/semantics/publishedVersion | es |
dc.rights.accessRights | info:eu-repo/semantics/openAccess | es |
dc.contributor.affiliation | Universidad de Sevilla. Departamento de Física Atómica, Molecular y Nuclear | es |
dc.relation.projectID | 633053 | es |
dc.relation.projectID | GA CR P205/12/2327 | es |
dc.relation.projectID | GA15-10723S | es |
dc.relation.projectID | MSMT LM2011021 | es |
dc.relation.projectID | DE-FG02- 07ER54917 | es |
dc.relation.projectID | DE-AC02-09CH11466 | es |
dc.relation.projectID | DE-FC02-04ER54698 | es |
dc.relation.publisherversion | http://dx.doi.org/10.1088/0741-3335/58/7/074005 | es |
dc.identifier.doi | 10.1088/0741-3335/58/7/074005 | es |
dc.contributor.group | Universidad de Sevilla. RNM138: Física Nuclear Aplicada | es |
dc.journaltitle | Contributions to Plasma Physics | es |
dc.publication.volumen | 58 | es |
dc.publication.issue | 7 | es |
dc.publication.initialPage | 074005 | es |