E.J.C. Tinacba , T.K. Gray , M. Moscheni , C. Marsden , E. Vekshina , O. Asunta , P. Bunting , S. McNamara , A. Rengle , T. Looby , E.A. Unterberg , ST40 Team
{"title":"HEAT simulation and IR data comparison for ST40 plasma-facing components","authors":"E.J.C. Tinacba , T.K. Gray , M. Moscheni , C. Marsden , E. Vekshina , O. Asunta , P. Bunting , S. McNamara , A. Rengle , T. Looby , E.A. Unterberg , ST40 Team","doi":"10.1016/j.nme.2024.101791","DOIUrl":null,"url":null,"abstract":"<div><div>The Heat Flux Engineering Analysis Toolkit (HEAT) (Looby et al., 2022) was used to simulate the heat flux, <span><math><msub><mrow><mi>q</mi></mrow><mrow><mi>t</mi><mi>a</mi><mi>r</mi><mi>g</mi><mi>e</mi><mi>t</mi></mrow></msub></math></span>, on ST40 molybdenum divertors. Results were compared with experimental infrared (IR) data. Two shots, 11419 and 11376 at time instants 119 ms and 120 ms, with lower-biased disconnected double null geometries, were studied. Single-<span><math><mi>λ</mi></math></span> and multi-<span><math><mi>λ</mi></math></span> heat flux profiles were used as input in HEAT simulation. The simulated <span><math><msub><mrow><mi>q</mi></mrow><mrow><mi>t</mi><mi>a</mi><mi>r</mi><mi>g</mi><mi>e</mi><mi>t</mi></mrow></msub></math></span> was used in OpenFOAM to calculate the corresponding temperature, <span><math><mi>T</mi></math></span>, on the divertors. Results showed that a good agreement on the simulated <span><math><msub><mrow><mi>q</mi></mrow><mrow><mi>t</mi><mi>a</mi><mi>r</mi><mi>g</mi><mi>e</mi><mi>t</mi></mrow></msub></math></span>, <span><math><mi>T</mi></math></span> and shape of the heat flux on the divertor with the IR data was achieved when a multi-<span><math><mi>λ</mi></math></span> heat flux profile was used for 11419, and single-<span><math><mi>λ</mi></math></span> heat flux profile for 11376. This indicates that HEAT can be reliable in analyzing and understanding the heat loading of plasma facing components in tokamak devices.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"41 ","pages":"Article 101791"},"PeriodicalIF":2.3000,"publicationDate":"2024-11-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Materials and Energy","FirstCategoryId":"101","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S235217912400214X","RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
The Heat Flux Engineering Analysis Toolkit (HEAT) (Looby et al., 2022) was used to simulate the heat flux, , on ST40 molybdenum divertors. Results were compared with experimental infrared (IR) data. Two shots, 11419 and 11376 at time instants 119 ms and 120 ms, with lower-biased disconnected double null geometries, were studied. Single- and multi- heat flux profiles were used as input in HEAT simulation. The simulated was used in OpenFOAM to calculate the corresponding temperature, , on the divertors. Results showed that a good agreement on the simulated , and shape of the heat flux on the divertor with the IR data was achieved when a multi- heat flux profile was used for 11419, and single- heat flux profile for 11376. This indicates that HEAT can be reliable in analyzing and understanding the heat loading of plasma facing components in tokamak devices.
期刊介绍:
The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.