CFETR 中性束注入系统负离子束源概念设计

doi:10.16568/j.0254-6086.202104008

核聚变与等离子体物理 ›› 2021, Vol. 41 ›› Issue (4): 628-634.DOI: 10.16568/j.0254-6086.202104008

CFETR 中性束注入系统负离子束源概念设计

谢亚红 1, 2，胡纯栋*1, 2，韦江龙 1，顾玉明 1，王圻 1, 2，梁立振 1, 2，蒋才超 1，许永建 1, 2，谢远来 1, 2，赵远哲 1

(1. 中国科学院等离子体物理研究所，合肥 230031；2. 中国科学技术大学，合肥 230026)

收稿日期:2020-03-29 修回日期:2020-11-28 出版日期:2021-12-15 发布日期:2022-01-11
作者简介:谢亚红(1982−)，男，安徽省合肥市人，博士，研究员，主要从事大功率离子源物理和实验研究。
基金资助:
国家重点研发计划资助(2017YFE0300503)

Conceptual design of negative ion based beam source for CFETR neutral beam injector

XIE Ya-hong1, 2, HU Chun-dong1, 2, WEI Jiang-long1, GU Yu-ming1, WANG Qi1, 2, LIANG Li-zhen1, 2, JIANG Cai-chao1, XU Yong-jian1, 2, XIE Yuan-lai1, 2, ZHAO Yuan-zhe1 #br#

(1. Institute of Plasma Physics, Chinese Academy of Science, Hefei 230031;
2. University of Science and Technology of China, Hefei 230026)

Received:2020-03-29 Revised:2020-11-28 Online:2021-12-15 Published:2022-01-11

摘要/Abstract

摘要： 根据 CFETR 对 NBI 系统参数的需求，开展了 CFETR NBI 束源的概念设计，给出了束源的设计参数指标和总体设计方案。完成了大面积等离子体发生器和负离子加速器两部分的设计工作。

关键词: CFETR, 中性束注入, 负离子束源, 加速器

Abstract: According to requirements of a neutral beam injector (NBI) system on China Fusion Engineering
Test Reactor (CFETR), the beam source for CFETR NBI system was designed. The overall concept design and
parameters were proposed. The designs of the large area plasma generator and the negative accelerator were
accomplished.

Key words: CFETR, Neutral beam injection, Negative ion based beam source, Accelerator

中图分类号:

TL62+9.1

谢亚红, 胡纯栋, 韦江龙, 顾玉明, 王圻, 梁立振, 蒋才超, 许永建, 谢远来, 赵远哲 . CFETR 中性束注入系统负离子束源概念设计 [J]. 核聚变与等离子体物理, 2021, 41(4): 628-634.

XIE Ya-hong, , HU Chun-dong, , WEI Jiang-long, GU Yu-ming, WANG Qi, , LIANG Li-zhen, , JIANG Cai-chao, XU Yong-jian, , XIE Yuan-lai, , ZHAO Yuan-zhe . Conceptual design of negative ion based beam source for CFETR neutral beam injector[J]. Nuclear Fusion and Plasma Physics, 2021, 41(4): 628-634.

参考文献

[1] Wan Y, Li J, Liu Y, et al. Overview of the present progress and activities on the CFETR [J]. Nucl. Fusion,2017, 57(10): 102009.
[2] de Esch H P L, Kashiwagi M, Taniguchi M, et al. Physics design of the HNB accelerator for ITER [J]. Nucl. Fusion, 2015, 55(9): 096001.
[3] Singh M J, Boilson D, Hemsworth R S, et al. Heating neutral beams for ITER: Present Status [J]. IEEE T Plasma Sci., 2016, 44(9): 1496−1505.
[4] Sonato P, Agostinetti P, Bolzonella T, et al., Conceptual design of the DEMO neutral beam injectors: main developments and R&D achievements [J]. Nucl. Fusion, 2017, 57(5): 056026.
[5] Sonato P, Agostinetti P, Fantz U, et al. Conceptual design of the beam source for the DEMO neutral beam injectors[J]. New J. Phys., 2016, 18(12): 125002.
[6] Hanada M, Kojima A, Tobari H, et al. Development of the negative ion beams relevant to ITER and JT-60SA at Japan atomic energy agency [J]. Rev. Sci. Instrum., 2016, 87(2): 02B322.
[7] Agostinetti P, Aprile D, Antoni V, et al. Detailed design optimization of the MITICA negative ion accelerator in view of the ITER NBI [J]. Nucl. Fusion, 2016, 56(1):016015.
[8] Marcuzzi D, Agostinetti P, Dalla Palma M, et al. Design of the RF ion source for the ITER NBI [J]. Fusion Eng.Des., 2007, 82(5−14): 798−805.
[9] Antoni V, Agostinetti P, Aprile D, et al. Physics design of the injector source for ITER neutral beam injector(invited) [J]. Rev. Sci. Instrum., 2014, 85(2): 02B128.
[10] Fantz U, Hopf C, Wunderlich D, et al. Towards powerful negative ion beams at the test facility ELISE for the ITER and DEMO NBI systems [J]. Nucl. Fusion, 2017,57(11): 116007.
[11] Wunderlich D, Riedl R, Bonomo F, et al. Achievement of ITER-relevant accelerated negative hydrogen ion current densities over 1000s at the ELISE test facility [J]. Nucl.Fusion, 2019, 59(8): 084001.
[12] Heinemann B, Wunderlich D, Kraus W, et al.Achievements of the ELISE test facility in view of the ITER NBI [J]. Fusion Eng. Des., 2019, 146: 455−459.
[13] Toigo V, Piovan R, Dal Bello S, et al. The PRIMA test facility: SPIDER and MITICA test-beds for ITER neutral beam injectors [J]. New J. Phys., 2017, 19(8): 085004.
[14] Serianni G, Toigo V, Bigi M, et al. SPIDER in the roadmap of the ITER neutral beams [J]. Fusion Eng. Des., 2019, 146: 2539−2546.
[15] Toigo V, Dal Bello S, Gaio E, et al. The ITER neutral beam test facility towards SPIDER operation [J]. Nucl.Fusion, 2017, 57(8): 086027.
[16] Marcuzzi D, Agostinetti P, Dalla Palma M, et al. Final design of the beam source for the MITICA injector [J]. Rev. Sci. Instrum., 2016, 87 (2): 02B309.
[17] Fellin F, Boldrin M, Zaccaria P, et al. Plant integration of MITICA and SPIDER experiments with auxiliary plants and buildings on PRIMA site [J]. Fusion Eng. Des., 2015,96−97: 257−260.
[18] Boeuf J P, Chaudhury B, Garrigues L. Physics of a magnetic filter for negative ion sources. I. Collisional transport across the filter in an ideal, 1D filter [J]. Phys. Plasmas, 2012, 19(11): 113509.
[19] Boeuf J P, Claustre J, Chaudhury B, et al. Physics of a magnetic filter for negative ion sources. II. E × B drift through the filter in a real geometry [J]. Phys. Plasmas,2012, 19(11): 113510.
[20] FR Schle M, Fantz U, Franzen P, et al. Magnetic filter field for ELISE––Concepts and design [J]. Fusion Eng.Des., 2013, 88(6−8): 1015−1019.
[21] Schiesko L, Cartry G, Hopf C, et al. Cs-doped Mo as surface converter for H−/D− generation in negative ion sources: first steps and proof of principle [C].International Symposium on Negative Ions, 2015,1655(1): 020003.
[22] Wada M, Doi K, Kenmotsu T. Impact due to impurity contamination upon Cs consumption of a negative hydrogen ion source [C]. Fifth International Symposium on Negative Ions, Beams and Sources (NIBS 2016), 2017, 1869(1): 020003.
[23] Singh M J, de Esch H P L, Hemsworth R, et al. Mo layer thickness requirement on the ion source back plate for the HNB and DNB ion sources in ITER [C]. Fourth International Symposium on Negative Ions, Beams and Sources (NIBS 2014), 2015, 1655: 040007.
[24] Kojima A, Tobari H, Umeda N, et al. Demonstration of 1 MV insulation for the vacuum insulated beam source in the ITER neutral beam system [J]. Nucl. Fusion, 2019, 59(8): 086042.
[25] Kojima A, Hanada M, Tobari H, et al. Development of design technique for vacuum insulation in large size multi-aperture multi-grid accelerator for nuclear fusion [J]. Rev. Sci. Instrum., 2016, 87(2): 02B304.

CFETR 中性束注入系统负离子束源概念设计

Conceptual design of negative ion based beam source for CFETR neutral beam injector

PDF

可视化

摘要/Abstract

引用本文

使用本文

参考文献

相关文章 15

编辑推荐

Metrics

[1]	班挺, 吴斌, 赵远哲, 崔庆龙, 谢亚红, 王泽 . 负离子源中性束注入系统打火瞬间关键信号高速数据采集系统设计[J]. 核工业西南物理研究院, 2024, 44(4): 423-428.
[2]	张立元, 王晓洁, 吴大俊, 汤允迎, 王瀚林, 刘甫坤 . CFETR ECRH 系统发射天线的初步结构设计与分析 [J]. 核工业西南物理研究院, 2024, 44(3): 267-274.
[3]	张西洋, 许铁军, 姚达毛 . CFETR 偏滤器低温泵抽气系统的设计和有效抽速的计算 [J]. 核工业西南物理研究院, 2024, 44(3): 275-281.
[4]	夏文颖, 杨雷, 胡纯栋, 郭斌, 朱黎黎, 李炜葆 . CRAFT NNBI 束源高温冷却水系统设计与分析[J]. 核工业西南物理研究院, 2024, 44(3): 297-303.
[5]	吉海标, 邢银龙, 吴杰峰, 刘志宏, 文伟, 林晓东 . 未来聚变堆绝缘材料 G10 放气性能测试与分析 [J]. 核工业西南物理研究院, 2024, 44(3): 318-322.
[6]	丁健, 李逸斌, 蒋才超, 宋士花, 刘胜, 段练, 徐康幸, 刘智民, 谢远来. 负离子源中性束注入器智慧能源管理系统设计[J]. 核工业西南物理研究院, 2024, 44(1): 30-35.
[7]	柴永生, 崔立民, 葛剑, 陈兆波, 张龙, 庞雪威. CFETR胀板式杜瓦冷屏的初步设计与热分析[J]. 核工业西南物理研究院, 2024, 44(1): 36-42.
[8]	高泽石, 王亚磊, 李彦龙, 田文喜, 才来中, 吴雪科, 连强, 李昕泽, 王占辉. 径向湍性输运条件下CFETR平行热通量及包层能量沉积模拟[J]. 核工业西南物理研究院, 2024, 44(1): 65-71.
[9]	杨明, 张新军, 李新霞, 吕波, 古敬仁. EAST低杂波加热对同向切向中性束碰撞力矩影响的研究[J]. 核工业西南物理研究院, 2024, 44(1): 92-97.
[10]	谢亚红, 谢俊炜, 韦江龙, 顾玉明, 蒋才超, 潘军军, 许永建, 谢远来, 胡纯栋. 大面积负离子束源磁过滤器的设计及实验研究 [J]. 核工业西南物理研究院, 2023, 43(4): 407-411.
[11]	於子辰, 陈玉庆, 许永建, 陈丽萍, 刘晓雪, 吴征威, 毛文哲 . 基于二次电子发射的中性束剖面诊断系统设计 [J]. 核工业西南物理研究院, 2023, 43(4): 457-461.
[12]	胡泊, 黄文玉, 周冰, 王晓宇, 王艳灵, 卢勇, 张龙, 刘宽程 . CFETR氦冷偏滤器回路 LOCA事故放射性释放分析[J]. 核聚变与等离子体物理, 2023, 43(2): 150-155.
[13]	杨文军, 龚学余, 高翔, 李小娥 . CFETR 上高能量粒子输运初步模拟研究[J]. 核聚变与等离子体物理, 2023, 43(2): 232-237.
[14]	王俊, 王占辉, 史永福, 李景春 . CFETR 稳态运行模式的 0.5 维集成模拟及其杂质粒子比例影响的分析 [J]. 核聚变与等离子体物理, 2023, 43(2): 243-248.
[15]	潘军军, 刘智民, 蒋才超, 刘胜, 陈世勇, 胡纯栋. 强流离子源灯丝电源设计与分析[J]. 核聚变与等离子体物理, 2023, 43(1): 50-54.