Hao Yang, Guido Ciraolo, Olivier Février, Nicolas Fedorczak, Nicolas Rivals, Andreas Bierwage, Hugo Bufferand, Gloria L Falchetto, Tomohide Nakano, Patrick Tamain, Jérôme Bucalossi, the WEST teama
{"title":"Numerical study of a general criterion for divertor detachment control","authors":"Hao Yang, Guido Ciraolo, Olivier Février, Nicolas Fedorczak, Nicolas Rivals, Andreas Bierwage, Hugo Bufferand, Gloria L Falchetto, Tomohide Nakano, Patrick Tamain, Jérôme Bucalossi, the WEST teama","doi":"10.1088/1741-4326/ad6e07","DOIUrl":null,"url":null,"abstract":"The parameter <inline-formula>\n<tex-math><?CDATA $R_\\mathrm{D} = P_\\mathrm{rad}/P_\\mathrm{cond}$?></tex-math><mml:math overflow=\"scroll\"><mml:mrow><mml:msub><mml:mi>R</mml:mi><mml:mrow><mml:mi mathvariant=\"normal\">D</mml:mi></mml:mrow></mml:msub><mml:mo>=</mml:mo><mml:msub><mml:mi>P</mml:mi><mml:mrow><mml:mi>rad</mml:mi></mml:mrow></mml:msub><mml:mrow><mml:mo>/</mml:mo></mml:mrow><mml:msub><mml:mi>P</mml:mi><mml:mrow><mml:mi>cond</mml:mi></mml:mrow></mml:msub></mml:mrow></mml:math><inline-graphic xlink:href=\"nfad6e07ieqn1.gif\"></inline-graphic></inline-formula>, which measures the ratio of radiated power to conductive heat flux at downstream <italic toggle=\"yes\">Scrape-Off-Layer</italic> (SOL), is proposed as a robust and practically useful figure of merit for divertor detachment control. The simulations performed using the SOLEDGE3X-EIRENE code predict that the instant where <inline-formula>\n<tex-math><?CDATA $R_\\mathrm{D}$?></tex-math><mml:math overflow=\"scroll\"><mml:mrow><mml:msub><mml:mi>R</mml:mi><mml:mrow><mml:mi mathvariant=\"normal\">D</mml:mi></mml:mrow></mml:msub></mml:mrow></mml:math><inline-graphic xlink:href=\"nfad6e07ieqn2.gif\"></inline-graphic></inline-formula> passes through unity (that is, when <inline-formula>\n<tex-math><?CDATA $P_\\mathrm{rad} \\approx P_\\mathrm{cond}$?></tex-math><mml:math overflow=\"scroll\"><mml:mrow><mml:msub><mml:mi>P</mml:mi><mml:mrow><mml:mi>rad</mml:mi></mml:mrow></mml:msub><mml:mo>≈</mml:mo><mml:msub><mml:mi>P</mml:mi><mml:mrow><mml:mi>cond</mml:mi></mml:mrow></mml:msub></mml:mrow></mml:math><inline-graphic xlink:href=\"nfad6e07ieqn3.gif\"></inline-graphic></inline-formula>) coincides with the detachment of the radiation front from the divertor target. Furthermore, as a function of <inline-formula>\n<tex-math><?CDATA $R_\\mathrm{D}$?></tex-math><mml:math overflow=\"scroll\"><mml:mrow><mml:msub><mml:mi>R</mml:mi><mml:mrow><mml:mi mathvariant=\"normal\">D</mml:mi></mml:mrow></mml:msub></mml:mrow></mml:math><inline-graphic xlink:href=\"nfad6e07ieqn4.gif\"></inline-graphic></inline-formula>, there is a decrease in target temperature and an increase in the distance at which the radiation front detaches from the target. These simulations cover scenarios in WEST and TCV with different levels of confinement, divertor closure, impurity concentration, and input power. The physical rationale underlying the above definition of <inline-formula>\n<tex-math><?CDATA $R_\\mathrm{D}$?></tex-math><mml:math overflow=\"scroll\"><mml:mrow><mml:msub><mml:mi>R</mml:mi><mml:mrow><mml:mi mathvariant=\"normal\">D</mml:mi></mml:mrow></mml:msub></mml:mrow></mml:math><inline-graphic xlink:href=\"nfad6e07ieqn5.gif\"></inline-graphic></inline-formula> is that when the divertor radiated power is comparable to the conductive heat flux, there will be a lack of energy reaching the target. Consequently, the radiation front detaches some distance from the divertor target. <inline-formula>\n<tex-math><?CDATA $R_\\mathrm{D}$?></tex-math><mml:math overflow=\"scroll\"><mml:mrow><mml:msub><mml:mi>R</mml:mi><mml:mrow><mml:mi mathvariant=\"normal\">D</mml:mi></mml:mrow></mml:msub></mml:mrow></mml:math><inline-graphic xlink:href=\"nfad6e07ieqn6.gif\"></inline-graphic></inline-formula> can thus be a good indicator for transitions to and from the detachment state. By monitoring <inline-formula>\n<tex-math><?CDATA $R_\\mathrm{D}$?></tex-math><mml:math overflow=\"scroll\"><mml:mrow><mml:msub><mml:mi>R</mml:mi><mml:mrow><mml:mi mathvariant=\"normal\">D</mml:mi></mml:mrow></mml:msub></mml:mrow></mml:math><inline-graphic xlink:href=\"nfad6e07ieqn7.gif\"></inline-graphic></inline-formula>, it becomes easier to maintain the heat flux deposition at the target at a manageable level. The evaluation of <inline-formula>\n<tex-math><?CDATA $R_\\mathrm{D}$?></tex-math><mml:math overflow=\"scroll\"><mml:mrow><mml:msub><mml:mi>R</mml:mi><mml:mrow><mml:mi mathvariant=\"normal\">D</mml:mi></mml:mrow></mml:msub></mml:mrow></mml:math><inline-graphic xlink:href=\"nfad6e07ieqn8.gif\"></inline-graphic></inline-formula> requires diagnostic measurement of downstream SOL radiation and upstream temperature which is feasible in tokamak devices. The robustness of this figure of merit is evaluated through realistic time-dependent numerical simulations for the WEST tokamak, as well as experimental data from WEST, TCV, and JT-60U cases. The results show that <inline-formula>\n<tex-math><?CDATA $R_\\mathrm{D}$?></tex-math><mml:math overflow=\"scroll\"><mml:mrow><mml:msub><mml:mi>R</mml:mi><mml:mrow><mml:mi mathvariant=\"normal\">D</mml:mi></mml:mrow></mml:msub></mml:mrow></mml:math><inline-graphic xlink:href=\"nfad6e07ieqn9.gif\"></inline-graphic></inline-formula> is capable of capturing the evolution of divertor plasma states, despite the different discharges and machines, suggesting that <inline-formula>\n<tex-math><?CDATA $R_\\mathrm{D}$?></tex-math><mml:math overflow=\"scroll\"><mml:mrow><mml:msub><mml:mi>R</mml:mi><mml:mrow><mml:mi mathvariant=\"normal\">D</mml:mi></mml:mrow></mml:msub></mml:mrow></mml:math><inline-graphic xlink:href=\"nfad6e07ieqn10.gif\"></inline-graphic></inline-formula> can serve as a valuable control variable for real-time experimental divertor detachment control.","PeriodicalId":19379,"journal":{"name":"Nuclear Fusion","volume":"63 1","pages":""},"PeriodicalIF":3.5000,"publicationDate":"2024-09-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Fusion","FirstCategoryId":"101","ListUrlMain":"https://doi.org/10.1088/1741-4326/ad6e07","RegionNum":1,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"PHYSICS, FLUIDS & PLASMAS","Score":null,"Total":0}
引用次数: 0
Abstract
The parameter RD=Prad/Pcond, which measures the ratio of radiated power to conductive heat flux at downstream Scrape-Off-Layer (SOL), is proposed as a robust and practically useful figure of merit for divertor detachment control. The simulations performed using the SOLEDGE3X-EIRENE code predict that the instant where RD passes through unity (that is, when Prad≈Pcond) coincides with the detachment of the radiation front from the divertor target. Furthermore, as a function of RD, there is a decrease in target temperature and an increase in the distance at which the radiation front detaches from the target. These simulations cover scenarios in WEST and TCV with different levels of confinement, divertor closure, impurity concentration, and input power. The physical rationale underlying the above definition of RD is that when the divertor radiated power is comparable to the conductive heat flux, there will be a lack of energy reaching the target. Consequently, the radiation front detaches some distance from the divertor target. RD can thus be a good indicator for transitions to and from the detachment state. By monitoring RD, it becomes easier to maintain the heat flux deposition at the target at a manageable level. The evaluation of RD requires diagnostic measurement of downstream SOL radiation and upstream temperature which is feasible in tokamak devices. The robustness of this figure of merit is evaluated through realistic time-dependent numerical simulations for the WEST tokamak, as well as experimental data from WEST, TCV, and JT-60U cases. The results show that RD is capable of capturing the evolution of divertor plasma states, despite the different discharges and machines, suggesting that RD can serve as a valuable control variable for real-time experimental divertor detachment control.
期刊介绍:
Nuclear Fusion publishes articles making significant advances to the field of controlled thermonuclear fusion. The journal scope includes:
-the production, heating and confinement of high temperature plasmas;
-the physical properties of such plasmas;
-the experimental or theoretical methods of exploring or explaining them;
-fusion reactor physics;
-reactor concepts; and
-fusion technologies.
The journal has a dedicated Associate Editor for inertial confinement fusion.