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Thermal FEA for alcator C-mod advanced outer divertor

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Thermal FEA for alcator C-mod advanced outer divertor. / Zhou, Lihua; Vieira, Rui; Harrison, Soren; Karnes, Dan; Lipschultz, Bruce.

In: IEEE transactions on plasma science, Vol. 42, No. 3, 6702504, 03.2014, p. 563-567.

Research output: Contribution to journalArticlepeer-review

Harvard

Zhou, L, Vieira, R, Harrison, S, Karnes, D & Lipschultz, B 2014, 'Thermal FEA for alcator C-mod advanced outer divertor', IEEE transactions on plasma science, vol. 42, no. 3, 6702504, pp. 563-567. https://doi.org/10.1109/TPS.2013.2295533

APA

Zhou, L., Vieira, R., Harrison, S., Karnes, D., & Lipschultz, B. (2014). Thermal FEA for alcator C-mod advanced outer divertor. IEEE transactions on plasma science, 42(3), 563-567. [6702504]. https://doi.org/10.1109/TPS.2013.2295533

Vancouver

Zhou L, Vieira R, Harrison S, Karnes D, Lipschultz B. Thermal FEA for alcator C-mod advanced outer divertor. IEEE transactions on plasma science. 2014 Mar;42(3):563-567. 6702504. https://doi.org/10.1109/TPS.2013.2295533

Author

Zhou, Lihua ; Vieira, Rui ; Harrison, Soren ; Karnes, Dan ; Lipschultz, Bruce. / Thermal FEA for alcator C-mod advanced outer divertor. In: IEEE transactions on plasma science. 2014 ; Vol. 42, No. 3. pp. 563-567.

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@article{55b3173ff6b041ae996a9bd907f99180,
title = "Thermal FEA for alcator C-mod advanced outer divertor",
abstract = "An advanced outer divertor is being developed for Alcator C-Mod to study reactor fuel (tritium) retention and plasma wall material interaction physics at reactor temperatures with high power long-pulse discharges. The divertor will be operated at controlled temperature of 60{\^0}C. To achieve this goal, the divertor will be structurally and electrically continuous along the toroidal direction, requiring it to expand radially as temperature increases. This paper describes the thermal finite element analysis (FEA) and results of the outer divertor. There are four aspects, with focus on the A-Frame assembly. First of all, a one twentieth module of the full divertor is composed of divertor tiles, tile mounting plate, heaters, divertor gusset, A-Frame support, spherical bearings, bracket, halo current shunt, vessel gusset, and so on. By adjusting the power of each of the seven toroidal divertor heaters, the tiles achieve a uniform temperature poloidally with toroidal temperature variation within allowables. The temperature of each component is evaluated, and results are used to support the design changes. Second, radiation simulation on multilayer radiation shields behind divertor plate is presented. Third, radiation simulation of the diverter heater itself is done to understand more details of heat transfer from the heater to the surrounding tiles and support plates. Finally, thermal analysis is completed with a model including a tile and its mounting plate, to predict the effect of plasma heat load on divertor tiles. All the thermal FEA was performed with COMSOL, a commercial FEA software.",
keywords = "Alcator C-Mod, heat transfer, outer divertor, plasma, thermal, tokamak",
author = "Lihua Zhou and Rui Vieira and Soren Harrison and Dan Karnes and Bruce Lipschultz",
year = "2014",
month = mar,
doi = "10.1109/TPS.2013.2295533",
language = "English",
volume = "42",
pages = "563--567",
journal = "IEEE transactions on plasma science",
issn = "0093-3813",
publisher = "Institute of Electrical and Electronics Engineers Inc.",
number = "3",

}

RIS (suitable for import to EndNote) - Download

TY - JOUR

T1 - Thermal FEA for alcator C-mod advanced outer divertor

AU - Zhou, Lihua

AU - Vieira, Rui

AU - Harrison, Soren

AU - Karnes, Dan

AU - Lipschultz, Bruce

PY - 2014/3

Y1 - 2014/3

N2 - An advanced outer divertor is being developed for Alcator C-Mod to study reactor fuel (tritium) retention and plasma wall material interaction physics at reactor temperatures with high power long-pulse discharges. The divertor will be operated at controlled temperature of 600̂C. To achieve this goal, the divertor will be structurally and electrically continuous along the toroidal direction, requiring it to expand radially as temperature increases. This paper describes the thermal finite element analysis (FEA) and results of the outer divertor. There are four aspects, with focus on the A-Frame assembly. First of all, a one twentieth module of the full divertor is composed of divertor tiles, tile mounting plate, heaters, divertor gusset, A-Frame support, spherical bearings, bracket, halo current shunt, vessel gusset, and so on. By adjusting the power of each of the seven toroidal divertor heaters, the tiles achieve a uniform temperature poloidally with toroidal temperature variation within allowables. The temperature of each component is evaluated, and results are used to support the design changes. Second, radiation simulation on multilayer radiation shields behind divertor plate is presented. Third, radiation simulation of the diverter heater itself is done to understand more details of heat transfer from the heater to the surrounding tiles and support plates. Finally, thermal analysis is completed with a model including a tile and its mounting plate, to predict the effect of plasma heat load on divertor tiles. All the thermal FEA was performed with COMSOL, a commercial FEA software.

AB - An advanced outer divertor is being developed for Alcator C-Mod to study reactor fuel (tritium) retention and plasma wall material interaction physics at reactor temperatures with high power long-pulse discharges. The divertor will be operated at controlled temperature of 600̂C. To achieve this goal, the divertor will be structurally and electrically continuous along the toroidal direction, requiring it to expand radially as temperature increases. This paper describes the thermal finite element analysis (FEA) and results of the outer divertor. There are four aspects, with focus on the A-Frame assembly. First of all, a one twentieth module of the full divertor is composed of divertor tiles, tile mounting plate, heaters, divertor gusset, A-Frame support, spherical bearings, bracket, halo current shunt, vessel gusset, and so on. By adjusting the power of each of the seven toroidal divertor heaters, the tiles achieve a uniform temperature poloidally with toroidal temperature variation within allowables. The temperature of each component is evaluated, and results are used to support the design changes. Second, radiation simulation on multilayer radiation shields behind divertor plate is presented. Third, radiation simulation of the diverter heater itself is done to understand more details of heat transfer from the heater to the surrounding tiles and support plates. Finally, thermal analysis is completed with a model including a tile and its mounting plate, to predict the effect of plasma heat load on divertor tiles. All the thermal FEA was performed with COMSOL, a commercial FEA software.

KW - Alcator C-Mod

KW - heat transfer

KW - outer divertor

KW - plasma

KW - thermal

KW - tokamak

UR - http://www.scopus.com/inward/record.url?scp=84896453484&partnerID=8YFLogxK

U2 - 10.1109/TPS.2013.2295533

DO - 10.1109/TPS.2013.2295533

M3 - Article

AN - SCOPUS:84896453484

VL - 42

SP - 563

EP - 567

JO - IEEE transactions on plasma science

JF - IEEE transactions on plasma science

SN - 0093-3813

IS - 3

M1 - 6702504

ER -