径向湍性输运条件下CFETR平行热通量及包层能量沉积模拟

doi:10.16568/j.0254-6086.202401011

核工业西南物理研究院 ›› 2024, Vol. 44 ›› Issue (1): 65-71.DOI: 10.16568/j.0254-6086.202401011

径向湍性输运条件下CFETR平行热通量及包层能量沉积模拟

高泽石1, 2，王亚磊3，李彦龙2，田文喜*1，才来中3，吴雪科3，连强1，李昕泽1，王占辉3

(1. 西安交通大学，西安 710049；2. 中国科学技术大学，合肥 230026；3. 核工业西南物理研究院，成都 610041)

收稿日期:2022-04-02 修回日期:2023-09-05 出版日期:2024-03-15 发布日期:2024-03-14
通讯作者: 田文喜(1979-)，男，山东巨野人，教授，博士研究生导师，从事反应堆热工水力与安全分析研究。
作者简介:高泽石(1999-)，男，陕西旬阳人，硕士研究生，从事等离子体与材料相互作用研究。
基金资助:
国家磁约束核聚变能发展研究专项(2018YFE0303102，2017YFE0302100)；四川省科技创新人才项目(2022JDRC0014)

Simulation of CFETR parallel heat flux and blanket power deposition under radial turbulent transport

GAO Ze-shi1, 2, WANG Ya-lei3, LI Yan-long2, TIAN Wen-xi1, CAI Lai-zhong3, WU Xue-ke3, LIAN Qiang1, LI Xin-ze1, WANG Zhan-hui3

(1. Xi’an Jiao Tong University, Xi’an 710049; 2. University of Science and Technology of China, Hefei 230026; 3. Southwestern Institute of Physics, Chengdu 610041)

Received:2022-04-02 Revised:2023-09-05 Online:2024-03-15 Published:2024-03-14

摘要/Abstract

摘要： 采用BOUT++输运程序与PFCFlux程序的耦合对CFETR包层第一壁上的能量沉积情况进行了模拟。研究发现，当湍性输运系数为50m²·s^‒1时，最外闭合磁面上的极向平均平行热通量为14058.5MW·m^‒2，进入刮削层的等离子体功率P_sol的值为197.4MW；CFETR包层第一壁上的能量沉积主要集中于真空室壁靠近中心螺线管的高场侧区域，最大热通量出现在这一区域的中间部分。

关键词: CFETR, BOUT++, PFCFlux, 平行热通量, 能量沉积

Abstract:

The power deposition on the first wall of the CFETR blanket is simulated with the PFCFlux program coupling the BOUT++ transport program. It is shown that when the radial turbulent transport coefficient is 50m²·s^‒1, the poloidal average parallel heat flux on the Last Closed Magnetic Surface is 14058.5MW·m^‒2, and the plasma power entering the scrape off layer is 197.4MW. The power deposition on the first wall of the CFETR blanket is mainly concentrated in the high field side region of the vacuum chamber wall close to the central solenoid, and the maximum heat flux occurs in the middle part of this region.

Key words: CFETR, BOUT++, PFCFlux, Parallel heat flux, Power deposition

中图分类号:

TL62+4

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.

GAO Ze-shi, , WANG Ya-lei, LI Yan-long, TIAN Wen-xi, CAI Lai-zhong, WU Xue-ke, LIAN Qiang, LI Xin-ze, WANG Zhan-hui. Simulation of CFETR parallel heat flux and blanket power deposition under radial turbulent transport[J]. Nuclear Fusion and Plasma Physics, 2024, 44(1): 65-71.

参考文献

[1] 李建刚. 托卡马克研究的现状及发展 [J]. 物理, 2016, 45(2): 88.
[2] Federici G, Bachmann C, Barucca L, et al. DEMO design activity in Europe: progress and updates [J]. Fusion Engineering and Design, 2018, 136: 729.
[3] Wan Y X, Li J G, Liu Y, et al. Overview of the present progress and activities on the CFETR [J]. Nuclear Fusion, 2017, 57(10): 102009.
[4] Zhuang G, Li G Q, Li J, et al. Progress of the CFETR design [J]. Nuclear Fusion, 2019, 59: 112010.
[5] 高翔, 万宝年, 宋云涛, 等. CFETR物理与工程研究进展 [J]. 中国科学: 物理学力学天文学, 2019, 49(4): 7.
[6] Liu S L, Pu Y, Cheng X M, et al. Conceptual design of a water cooled breeder blanket for CFETR [J]. Fusion Engineering and Design, 2014, 89(7-8): 1380.
[7] Wang S H, Cao Q X, Wu X H, et al. Updated conceptual design of helium cooling ceramic blanket for HCCB-DEMO [J]. Fusion Engineering and Design, 2016, 112: 148.
[8] Liu S L, Li X, Ma X B, et al. Updated design of water-cooled breeder blanket for CFETR [J]. Fusion Engineering and Design, 2019, 146: 1716.
[9] Moro F, Del Nevo A, Flammini D, et al. Neutronic analyses in support of the WCLL DEMO design development [J]. Fusion Engineering and Design, 2018, 136: 1260.
[10] Shimwell J, Lu L, Qiu Y, et al. Automated parametric neutronics analysis of the Helium Cooled Pebble Bed breeder blanket with Be12Ti [J]. Fusion Engineering and Design, 2017, 124: 940.
[11] Liu C L, Qiu Y, Zhang J, et al. Study on the temperature control mechanism of the tritium breeding blanket for CFETR [J]. Nuclear Fusion, 2017, 57(12): 124003.
[12] Dudson B D, Umansky M V, Xu X Q, et al. BOUT++: A framework for parallel plasma fluid simulations [J]. Computer Physics Communications, 2009, 180(9): 1467.
[13] Wang Z H, Xu X Q, Xia T Y, et al. 2D simulations of transport dynamics during tokamak fuelling by supersonic molecular beam injection [J]. Nuclear Fusion, 2014, 54(4): 43019.
[14] Wu X K, Li H D, Wang Z H, et al. Simulations of the effects of density and temperature profile on SMBI penetration depth based on the HL-2A tokamak configuration [J]. Chinese Physics B, 2017, 26(6): 65201.
[15] Li N M, Sun J Z, Wang Z H, et al. Numerical investigation on lithium transport in the edge plasma of EAST real-time- Li-injection experiments in the frame of BOUT++ [J]. Nuclear Materials and Energy, 2017, 12: 119.
[16] Wu X K, Wang Z H, Li H D, et al. Simulation of helium supersonic molecular beam injection in tokamak plasma [J]. Chinese Physics B, 2020, 29(6): 65201.
[17] Firdaouss M, Riccardo V, Martin V, et al. Modelling of power deposition on the JET ITER like wall using the code PFCFLux [J]. Journal of Nuclear Materials, 2013, 438: S536.
[18] Zhang B, Firdaouss M, Gong X Z, et al. Study of power load pattern on EAST divertor using PFCFlux code [J]. Fusion Engineering and Design, 2016, 107: 58.
[19] Nian F F, Yang Z S, Ding R, et al. Modelling of the complete heat flux deposition on the CFETR first wall with neon seeding [J]. Plasma Physics and Controlled Fusion, 2021, 63(9): 95004.
[20] Xia T Y, Xu X Q, Xi P W. Six-field two-fluid simulations of peeling-ballooning modes using BOUT++ [J]. Nuclear fusion, 2013, 53(4): 73009.
[21] Chen J L, Chan V S, Jian X, et al. Integrated modeling of CFETR hybrid scenario plasmas [J]. Nuclear Fusion, 2021, 61(4): 46002.
[22] Eich T, Leonard A W, Pitts R A, et al. Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER [J]. Nuclear Fusion, 2013, 53(9): 93031.
[23] Wenninger R, Albanese R, Ambrosino R, et al. The DEMO wall load challenge [J]. Nuclear Fusion, 2017, 57(4): 46002.

径向湍性输运条件下CFETR平行热通量及包层能量沉积模拟

Simulation of CFETR parallel heat flux and blanket power deposition under radial turbulent transport

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]	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.
[2]	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.
[3]	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.
[4]	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.
[5]	钟云珂, 陈鑫, 朱根良, 杨恩朋, 付猷昆, 蔡立君, 李强 . CFETR 25kW 4.5K 氦制冷机 RAMI 初步分析[J]. 核聚变与等离子体物理, 2023, 43(1): 55-61.
[6]	邑伟, 胡纯栋, 谢远来, 谢亚红, 刘伟, 韦江龙, 顾玉明, 梁立振, 陶玲, 崔庆龙, 赵远哲, 蒋才超, 许永建, . CFETR N-NBI 验证样机恒温供水系统的设计[J]. 核聚变与等离子体物理, 2023, 43(1): 62-67.
[7]	郝保龙, 陈伟, 李国强, 王晓静, 吴斌, 高翔, CFETR TEAM . 高能量粒子再分布模型在 CFETR 上的应用[J]. 核聚变与等离子体物理, 2023, 43(1): 105-111.
[8]	宋强, 杨锦宏, 陆野, 桂腾, 汪卫华 . CFETR雪花偏滤器位形放电模拟及电磁仿真分析[J]. 核聚变与等离子体物理, 2022, 42(s1): 144-151.
[9]	许婉韵, 王才旺, 罗蓉蓉, 黄超, 李鹏远, 许发勇, 邓华林, 陈辉. CFETR 产氚包层与偏滤器部件在热室内维修与退役流程的概念设计[J]. 核聚变与等离子体物理, 2022, 42(4): 378-382.
[10]	胡纯栋, 梁立振, 谢远来, 谢亚红, 韦江龙, 顾玉明, 蒋才超, 许永建, 赵远哲, 陈玉庆 . CFETR 中性束注入系统概念设计[J]. 核聚变与等离子体物理, 2022, 42(4): 388-392.
[11]	王文嘉, 成晓曼, 马学斌, 刘松林. CFETR 水冷包层模块真空室内破口事故安全分析[J]. 核聚变与等离子体物理, 2022, 42(4): 433-439.
[12]	罗蓉蓉, 潘传杰, 王才旺, 李鹏远, 王晓宇, 邓华林, 闫腾飞, 许发勇, 许婉韵. CFETR包层在热室内的除氚流程初步设计[J]. 核聚变与等离子体物理, 2022, 42(3): 279-284.
[13]	凌启鑫, 马学斌, 刘松林. CFETR水冷包层模块热工水力学分析与优化[J]. 核聚变与等离子体物理, 2022, 42(3): 301-307.
[14]	李航, 谢海, 李国强, 陈佳乐, 钱金平, 高翔, 黄建军. CFETR混杂模式下的准雪花平衡位形设计[J]. 核聚变与等离子体物理, 2022, 42(3): 361-366.
[15]	金环, 武玉, 施毅, 秦经刚, 刘辰, 戴超, 张雍良, 刘华军. CFETR馈线导体设计与热稳定性分析[J]. 核聚变与等离子体物理, 2022, 42(2): 182-186.