S. Sureshkumar , N. Rivals , P. Tamain , X. Bonnin , R. Pitts , Y. Marandet , G. Ciraolo , H. Bufferand , G. Falchetto , N. Fedorczak , V. Quadri , M. Raghunathan , F. Schwander , E. Serre , R. Düll , N. Varadarajan
{"title":"First SOLEDGE3X-EIRENE simulations of the ITER Neon seeded burning plasma boundary up to the first wall","authors":"S. Sureshkumar , N. Rivals , P. Tamain , X. Bonnin , R. Pitts , Y. Marandet , G. Ciraolo , H. Bufferand , G. Falchetto , N. Fedorczak , V. Quadri , M. Raghunathan , F. Schwander , E. Serre , R. Düll , N. Varadarajan","doi":"10.1016/j.nme.2024.101780","DOIUrl":null,"url":null,"abstract":"<div><div>Boundary plasma simulations are essential to estimate expected divertor and first wall (FW) heat and particle loads on ITER during burning plasma operation. A key missing feature of existing SOLPS simulations (Pitts et al., 2019) is the absence of a plasma solution out to the main chamber walls, essential to self-consistently estimate the gross sputtering of wall material. Here, SOLEDGE3X is applied for the first time to obtain up-to-the wall burning plasma solutions of the ITER boundary plasma at the nominal <span><math><msub><mrow><mi>P</mi></mrow><mrow><mi>S</mi><mi>O</mi><mi>L</mi></mrow></msub></math></span> = 100 MW of the main SOLPS database simulations, including He ash, Ne seeding but without fluid drifts. Compared with the most recent SOLPS-ITER simulations, our simulations show differences in the exact impurity distribution, but the key results for divertor and wall heat flux remain consistent. In the context of the ITER re-baselining exercise (Pitts, 2024), in which the Be FW armour is proposed to be exchanged for tungsten (W), estimates of W wall sources are key to the assessment of likely core contamination and hence impact on fusion gain. We compare the W gross erosion rates due to the different species excluding W self-sputtering. For the cases simulated spanning 0.27%–0.47% separatrix-averaged Ne concentration and <span><math><mrow><mn>7</mn><mo>.</mo><mn>5</mn><mo>×</mo><mn>1</mn><msup><mrow><mn>0</mn></mrow><mrow><mn>22</mn></mrow></msup><mspace></mspace><msup><mrow><mi>s</mi></mrow><mrow><mo>−</mo><mn>1</mn></mrow></msup><mo>−</mo><mn>1</mn><mo>.</mo><mn>95</mn><mo>×</mo><mn>1</mn><msup><mrow><mn>0</mn></mrow><mrow><mn>23</mn></mrow></msup><mspace></mspace><msup><mrow><mi>s</mi></mrow><mrow><mo>−</mo><mn>1</mn></mrow></msup></mrow></math></span> D fuelling, <span><math><msup><mrow><mtext>Ne</mtext></mrow><mrow><mn>8</mn><mo>+</mo></mrow></msup></math></span> remains the largest contributor to the sputtering flux with the largest source being the outer divertor and baffle. The species-wise contribution to W sputtering changes with fuelling with sputtering due to lower Ne charge states being significant at low D fuelling. In general, the gross W sputtering source is found to decrease with increase in D fuelling and increase with increased Ne seeding.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"41 ","pages":"Article 101780"},"PeriodicalIF":2.3000,"publicationDate":"2024-10-23","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/S2352179124002035","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
Boundary plasma simulations are essential to estimate expected divertor and first wall (FW) heat and particle loads on ITER during burning plasma operation. A key missing feature of existing SOLPS simulations (Pitts et al., 2019) is the absence of a plasma solution out to the main chamber walls, essential to self-consistently estimate the gross sputtering of wall material. Here, SOLEDGE3X is applied for the first time to obtain up-to-the wall burning plasma solutions of the ITER boundary plasma at the nominal = 100 MW of the main SOLPS database simulations, including He ash, Ne seeding but without fluid drifts. Compared with the most recent SOLPS-ITER simulations, our simulations show differences in the exact impurity distribution, but the key results for divertor and wall heat flux remain consistent. In the context of the ITER re-baselining exercise (Pitts, 2024), in which the Be FW armour is proposed to be exchanged for tungsten (W), estimates of W wall sources are key to the assessment of likely core contamination and hence impact on fusion gain. We compare the W gross erosion rates due to the different species excluding W self-sputtering. For the cases simulated spanning 0.27%–0.47% separatrix-averaged Ne concentration and D fuelling, remains the largest contributor to the sputtering flux with the largest source being the outer divertor and baffle. The species-wise contribution to W sputtering changes with fuelling with sputtering due to lower Ne charge states being significant at low D fuelling. In general, the gross W sputtering source is found to decrease with increase in D fuelling and increase with increased Ne seeding.
边界等离子体模拟对于估算燃烧等离子体运行期间热核聚变实验堆上的预期分流器和第一壁(FW)热负荷和粒子负荷至关重要。现有 SOLPS 仿真(Pitts 等人,2019 年)缺少的一个关键特征是缺少主室壁外的等离子体解决方案,而这对于自洽地估算壁材料的总溅射量至关重要。在这里,SOLEDGE3X 被首次应用于在主要 SOLPS 数据库模拟的标称 PSOL = 100 MW 条件下获得热核实验堆边界等离子体的直至壁面燃烧的等离子体解,包括 He ash、Ne seeding,但不包括流体漂移。与最新的 SOLPS-ITER 模拟相比,我们的模拟在杂质的精确分布方面存在差异,但岔流和壁面热通量的关键结果保持一致。在国际热核聚变实验堆(ITER)重新换衬底工作(Pitts,2024 年)的背景下,建议将铍 FW 盔甲换成钨(W),对 W 壁源的估计是评估可能的堆芯污染并进而影响核聚变增益的关键。我们比较了不同种类(不包括 W 自溅射)造成的 W 总侵蚀率。在跨越 0.27%-0.47% 分离矩阵平均 Ne 浓度和 7.5×1022s-1-1.95×1023s-1 D 燃料的模拟情况下,Ne8+ 仍然是溅射通量的最大贡献者,而最大的来源是外部分流器和挡板。对 W 溅射的物种贡献随燃料量的变化而变化,在低 D 燃料量下,较低的 Ne 电荷态对溅射的贡献很大。一般来说,W 溅射源总量会随着 D 注入量的增加而减少,并随着 Ne 注入量的增加而增加。
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.