Wall conditions in WEST during operations with a new ITER grade, actively cooled divertor

IF 2.3 2区 物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Materials and Energy Pub Date : 2024-09-19 DOI:10.1016/j.nme.2024.101741
A. Gallo , Ph. Moreau , D. Douai , T. Alarcon , K. Afonin , V. Anzallo , R. Bisson , J. Bucalossi , E. Caprin , Y. Corre , M. De Combarieu , C. Desgranges , P. Devynck , A. Ekedahl , N. Fedorczak , J. Gaspar , A. Grosjean , C. Guillemaut , R. Guirlet , J.P. Gunn , A. Widdowson
{"title":"Wall conditions in WEST during operations with a new ITER grade, actively cooled divertor","authors":"A. Gallo ,&nbsp;Ph. Moreau ,&nbsp;D. Douai ,&nbsp;T. Alarcon ,&nbsp;K. Afonin ,&nbsp;V. Anzallo ,&nbsp;R. Bisson ,&nbsp;J. Bucalossi ,&nbsp;E. Caprin ,&nbsp;Y. Corre ,&nbsp;M. De Combarieu ,&nbsp;C. Desgranges ,&nbsp;P. Devynck ,&nbsp;A. Ekedahl ,&nbsp;N. Fedorczak ,&nbsp;J. Gaspar ,&nbsp;A. Grosjean ,&nbsp;C. Guillemaut ,&nbsp;R. Guirlet ,&nbsp;J.P. Gunn ,&nbsp;A. Widdowson","doi":"10.1016/j.nme.2024.101741","DOIUrl":null,"url":null,"abstract":"<div><div>Future fusion reactors like ITER and DEMO will have all-tungsten (W) walls and long pulses. These features will make wall conditioning more difficult than in most of the existing devices. The W Environment Steady-state Tokamak (WEST) is one of the few long pulse (364 s) fusion devices with actively cooled W plasma-facing components in the world. WEST is a unique test bed to study impurity migration and plasma density control via reactor relevant wall conditioning techniques. The phase II of WEST operations began in 2022, after the installation of a new lower divertor, now entirely equipped with actively cooled, ITER grade, W monoblocks. After pump down, we baked WEST between 90 °C and 170 °C for ∼2 weeks. After 82.5 h at 90 °C and 33 h at 170 °C, vacuum conditions were stable with a vessel pressure of 6x10<sup>-5</sup> Pa and mass spectra dominated by H<sub>2</sub> molecules. While at 170 °C, we performed ∼40 h of D<sub>2</sub> glow discharge cleaning (GDC) and ∼5 h of glow discharge boronization (GDB), using a 15 %-85 % B<sub>2</sub>D<sub>6</sub>-He mix and a total boron mass of ∼12 g. This was the very first GDB at such high temperature for WEST. The whole wall conditioning sequence led to a ∼10 times reduction of the H<sub>2</sub>O signal as well as to a ∼3 times reduction of the O<sub>2</sub> signal, according to mass spectra. Once back to 70 °C, the vessel pressure was 5.5x10<sup>-6</sup> Pa and plasma restart was seamless with ∼30 s cumulated over the very first 5 pulses and an Ohmic radiated power fraction F<sub>rad</sub> = 0.6, showing successful conditioning of the new ITER grade divertor. The effect of the first, ‘hot’ GDB faded with a characteristic cumulative injected energy of 2.45 GJ and saturation towards F<sub>rad</sub> ∼0.8. After 1.4 h and 7.5 GJ of cumulative plasma time and injected energy, we carried out a second GDB, this time at 70 °C. This ‘cold’ GDB initially led to a much lower Ohmic F<sub>rad</sub> = 0.3–0.4 but the effect lasted ∼7 times less, with a characteristic cumulative injected energy of 0.37 GJ. At the end of the campaign, we cumulated ∼3h and ∼30 GJ through repetitive, minute long pulses without any boronization. Throughout this 4-weeks-long experiment, F<sub>rad</sub> in the 4 MW heating phase evolved only marginally (from 0.5 to 0.55). This increase is mostly due to the build-up of re/co-deposited layers on both lower divertor targets.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"41 ","pages":"Article 101741"},"PeriodicalIF":2.3000,"publicationDate":"2024-09-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2352179124001649/pdfft?md5=3912a6c3700db6f4c6469e71864a572c&pid=1-s2.0-S2352179124001649-main.pdf","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Materials and Energy","FirstCategoryId":"101","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S2352179124001649","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

Future fusion reactors like ITER and DEMO will have all-tungsten (W) walls and long pulses. These features will make wall conditioning more difficult than in most of the existing devices. The W Environment Steady-state Tokamak (WEST) is one of the few long pulse (364 s) fusion devices with actively cooled W plasma-facing components in the world. WEST is a unique test bed to study impurity migration and plasma density control via reactor relevant wall conditioning techniques. The phase II of WEST operations began in 2022, after the installation of a new lower divertor, now entirely equipped with actively cooled, ITER grade, W monoblocks. After pump down, we baked WEST between 90 °C and 170 °C for ∼2 weeks. After 82.5 h at 90 °C and 33 h at 170 °C, vacuum conditions were stable with a vessel pressure of 6x10-5 Pa and mass spectra dominated by H2 molecules. While at 170 °C, we performed ∼40 h of D2 glow discharge cleaning (GDC) and ∼5 h of glow discharge boronization (GDB), using a 15 %-85 % B2D6-He mix and a total boron mass of ∼12 g. This was the very first GDB at such high temperature for WEST. The whole wall conditioning sequence led to a ∼10 times reduction of the H2O signal as well as to a ∼3 times reduction of the O2 signal, according to mass spectra. Once back to 70 °C, the vessel pressure was 5.5x10-6 Pa and plasma restart was seamless with ∼30 s cumulated over the very first 5 pulses and an Ohmic radiated power fraction Frad = 0.6, showing successful conditioning of the new ITER grade divertor. The effect of the first, ‘hot’ GDB faded with a characteristic cumulative injected energy of 2.45 GJ and saturation towards Frad ∼0.8. After 1.4 h and 7.5 GJ of cumulative plasma time and injected energy, we carried out a second GDB, this time at 70 °C. This ‘cold’ GDB initially led to a much lower Ohmic Frad = 0.3–0.4 but the effect lasted ∼7 times less, with a characteristic cumulative injected energy of 0.37 GJ. At the end of the campaign, we cumulated ∼3h and ∼30 GJ through repetitive, minute long pulses without any boronization. Throughout this 4-weeks-long experiment, Frad in the 4 MW heating phase evolved only marginally (from 0.5 to 0.55). This increase is mostly due to the build-up of re/co-deposited layers on both lower divertor targets.
查看原文
分享 分享
微信好友 朋友圈 QQ好友 复制链接
本刊更多论文
新型 ITER 级主动冷却分流器运行期间 WEST 的壁况
未来的聚变反应堆(如 ITER 和 DEMO)将采用全钨(W)壁和长脉冲。这些特点将使炉壁调节比大多数现有设备更加困难。钨环境稳态托卡马克(WEST)是世界上为数不多的长脉冲(364 秒)核聚变装置之一,其面向钨等离子体的部件都是主动冷却的。WEST 是研究杂质迁移和通过反应堆相关壁调节技术控制等离子体密度的独特试验台。WEST 的第二阶段运行始于 2022 年,当时安装了一个新的下部分流器,现在完全配备了主动冷却的 ITER 级 W 单体。停泵后,我们在 90 °C 和 170 °C 之间对 WEST 进行了 2 周的烘烤。在 90 °C 烘烤 82.5 小时和 170 °C 烘烤 33 小时后,真空条件稳定,容器压力为 6x10-5 Pa,质谱以 H2 分子为主。在 170 ℃ 时,我们进行了 40 小时的 D2 辉光放电清洗(GDC)和 5 小时的辉光放电硼化(GDB),使用了 15 %-85 % 的 B2D6-He 混合物,硼的总质量为 12 克。根据质谱显示,整个壁面调节过程导致 H2O 信号减少了 ∼ 10 倍,O2 信号减少了 ∼ 3 倍。当温度恢复到 70 °C,容器压力为 5.5x10-6 Pa,等离子体无缝重启,前 5 个脉冲的累积时间为 30 秒,欧姆辐射功率分数 Frad = 0.6,这表明新的热核实验堆级分流器的调节成功。第一个 "热 "GDB 的影响逐渐减弱,特征累积注入能量为 2.45 GJ,饱和度达到 Frad ∼0.8。经过 1.4 小时和 7.5 GJ 的累积等离子体时间和注入能量后,我们进行了第二次 GDB,这次的温度为 70 °C。这次 "冷 "GDB 最初的欧姆 Frad = 0.3-0.4 要低得多,但效果持续时间要短 7 倍,特征累积注入能量为 0.37 GJ。活动结束时,我们通过重复的、长达一分钟的脉冲累积了 ∼3 小时和 ∼30 GJ 的能量,但没有发生任何硼化现象。在为期 4 周的实验中,4 兆瓦加热阶段的 Frad 变化不大(从 0.5 到 0.55)。这一增长主要是由于在两个下岔道靶上重新/共沉积层的形成。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
求助全文
约1分钟内获得全文 去求助
来源期刊
Nuclear Materials and Energy
Nuclear Materials and Energy Materials Science-Materials Science (miscellaneous)
CiteScore
3.70
自引率
15.40%
发文量
175
审稿时长
20 weeks
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.
期刊最新文献
Theoretical investigation of structural, electronic, mechanical, surface work function and thermodynamic properties of La1-xMxB6 (M = Ba, Sr, Ca) compounds: Potential plasma grid materials in N-NBI system Study of spectral features and depth distributions of boron layers on tungsten substrates by ps-LIBS in a vacuum environment Initial design concepts for solid boron injection in ITER Utilization of D2 molecular band emission for electron density measurement Fast prediction of irradiation-induced cascade defects using denoising diffusion probabilistic model
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
现在去查看 取消
×
提示
确定
0
微信
客服QQ
Book学术公众号 扫码关注我们
反馈
×
意见反馈
请填写您的意见或建议
请填写您的手机或邮箱
已复制链接
已复制链接
快去分享给好友吧!
我知道了
×
扫码分享
扫码分享
Book学术官方微信
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术
文献互助 智能选刊 最新文献 互助须知 联系我们:info@booksci.cn
Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。
Copyright © 2023 Book学术 All rights reserved.
ghs 京公网安备 11010802042870号 京ICP备2023020795号-1