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Confinement of fusion born alpha particles in tokamak is the key issue to burning plasma. Apart from toroidal field ripple, instabilities can induce energetic particles to lose and be redistributed. Based on the parameters of China Fusion Engineering Testing Reactor (CFETT) hybrid scenario, alpha particle distribution and neoclassical tearing mode structure, the alpha particle loss induced under perturbation of ripple and neoclassical tearing mode (NTM) is calculated with the guiding center code ORBIT. The inputs have the initial distribution of alpha particles which is obtained with the TRANSP/NUBEAM code, the static NTM perturbation with different amplitudes which is obtained from TM1 code, and the ripple field from engineering design. The results show that the heat load on last closed flux surface is about 0.1 MW/m2, with ripple and collision included. The collisionless stochastic ripple diffusion is the main loss channel of initial alpha particle distribution in the CFETR, and the ripple perturbation has no influence on passing particles. The loss fraction does not increase with the NTM perturbation amplitude increasing, the synergistic effect is negligible. The scanning of ripple amplitude shows that the synergistic effect is slight. The monoenergetic initial distribution of alpha particles can give different types of orbits in the plane of (
$ {P_\zeta },\mu $ ), such as the domains of trapped particle and passing particle, lost particle and confined particle. The trapped fraction of initial alpha particles is about 27%, ripple loss region in phase space is narrow and away from the main trapped particle distribution. The increasing of ripple perturbation in simulation does enlarge the ripple loss domain in the phase space ($ {P_\zeta },\mu $ ), which is corresponding to a lager ripple loss fraction and has more trapped-passing boundaries. The NTM perturbation does enlarge the orbit excursions of trapped particles, and thus increasing the trapped passing transition near the boundary. The slight synergistic effect in calculation with larger ripple amplitude is explained by ripple loss region having more trapped-passing boundaries, not by the profile flattening of trapped particles. The NTM perturbation and finite collision can transit the passing particle to trapped particle near the boundary. With the help of kinetic Poincare plot, neither direct particle loss nor profile flattening of trapped particles is observed. The loss fraction enhancement can happen only when the profile flattening of trapped particles takes place within the ripple loss region, which is not the case in CFETR. The conclusion of this work contributes a lot to the design of CFETR and the study of alpha particle physics.-
Keywords:
- tokamak /
- alpha particle /
- magnetic ripple /
- neoclassical tearing mode
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Google Scholar
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Google Scholar
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Google Scholar
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Google Scholar
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Google Scholar
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[20] Yu Q, Gunter S, Scott B D 2003 Phys. Plasmas. 10 798
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Google Scholar
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Google Scholar
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Google Scholar
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图 1 CFETR混杂运行模式(v201806)中背景电子密度、温度和离子温度分布
Figure 1. Distributions of bulk electron density, electron temperature, and bulk ion temperature in CFETR hybrid scenario (v201806).
图 2 CFETR初始alpha粒子密度分布
Figure 2. Density profile of alpha particle initial distribution in CFETR.
图 3 CFETR纵场波纹度分布 (a) 解析函数实现值; (b) 工程设计值
Figure 3. Distributions of toroidal field ripple perturbation amplitude in CFETR: (a) Ripple data by analytical equation; (b) engineering data in design.
图 4 CFETR混杂运行模式 (a) 2/1和3/2 NTM的平衡分量和安全因子分布; (b), (c)一阶分量和高斯拟合曲线
Figure 4. (a) Safety factor profile and equilibrium helical flux of 2/1 and 3/2 NTM in CFETR hybrid scenario; (b), (c) the first order harmonics and Gaussian fitting results.
图 5 固定2/1和3/2模扰动幅度比例下扫描NTM扰动幅度下的庞加莱图 (a)
${\alpha _{2/1}} = 1.64 \times {10^{ - 4}}{R_0}$ ; (b)${\alpha _{2/1}} = l $ $ 6.00 \times {10^{ - 4}}{R_0}$ Figure 5. Poincare plot under different NTM perturbation amplitude with the ratio fixed
${{{\alpha _{2/1}}} / {{\alpha _{3/2}}}} = 4.38$ : (a)${\alpha _{2/1}} = $ $ 1.64 \times {10^{ - 4}}{R_0}$ ; (b)${\alpha _{2/1}} = 6.00 \times {10^{ - 4}}{R_0}$ .
图 6 在半个EP慢化时间内不同物理效应下计算得到的粒子损失份额
Figure 6. The particle loss fraction after following half a slowing down time under different perturbation and collision.
图 7 纵场波纹扰动下损失alpha粒子信息 (a) 损失份额随时演化; (b) 损失粒子能量分布; (c) 损失粒子螺距角分布
Figure 7. Information of lost alpha particles under collision and toroidal field ripple: (a) Evolution of loss fraction; (b) energy distribution of lost particles; (c) pitch angle distribution of lost particles.
图 8 一个慢化时间后初始分布alpha粒子波纹损失局域沉积在LCFS处得到的热负荷
Figure 8. The heat load at the last closed flux surface due to ripple loss of initial alpha particle distribution after a slowing down time.
图 14 初始分布alpha粒子香蕉轨道漂移频率分布 (a) 极向回弹频率; (b) 环向进动频率
Figure 14. The drift frequency distributions of banana orbit of initial alpha particles: (a) Poloidal bounce frequency; (b) toroidal precession frequency.
图 9 同向alpha粒子动理学庞加莱图 (a) 通行粒子; (b) 俘获粒子
Figure 9. The kinetic Poincare plot of co-current alpha particles: (a) Passing particle; (b) trapped particle.
图 10 半个慢化时间内不同磁场波纹度和NTM扰动幅度下的初始分布alpha粒子损失份额
Figure 10. The loss fraction of initial alpha particles under different toroidal ripple and NTM perturbation amplitude.
图 11 CFETR平衡位形中不同波纹度形成的波纹磁阱 (a) 工程设计值; (b) 5倍波纹度分布; (c) 9倍波纹度分布
Figure 11. The ripple well domain in CFETR equilibrium with different ripple amplitude: (a) Distribution with engineering design; (b) 5 times of ripple; (c) 9 times of ripple.
图 12 (a) (
${P_{\zeta} }, {{\mu {B_0}} / E}$ )平面初始alpha粒子轨道类型分布; (b) 正值螺距角粒子分布; (c) 负值螺距角粒子分布Figure 12. (a) Orbit classification in the plane of
$({P_{\zeta} }, {{\mu {B_0}} / E})$ with initial alpha particles; (b) particles with positive pitch angle; (c) particles with negative pitch angle.
图 13 不同倍数波纹度分布时的波纹磁阱和随机波纹扩散区域 (a), (b) 工程设计值; (c), (d) 5倍波纹度分布; (e), (f) 9倍波纹度分布
Figure 13. The ripple well trapping and stochastic ripple diffusion domain with different times of ripple distribution: (a), (b) Ripple in engineering design; (c), (d) 5 times of ripple; (e), (f) 9 times of ripple.
表 1 CFETR与其他托卡马克装置主机参数对比
Table 1. Main parameters comparison of CFETR and other tokomak facilities.
参数 CFETR ITER EAST 磁轴场强${B_{{\rm{T}}0}}$/T 6.5 5.3 2 等体大半径${R_0}$/m 7.2 6.2 1.9 等体小半径a/m 2.2 2.0 0.5 等体电流${I_{\rm{p}}}$/MA 14 15 1 纵场磁体柄数N 16 18 16 
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[1] Zhuang G, Li G Q, Li J, et al. 2019 Nucl. Fusion 59 112010
Google Scholar
[2] Wan Y X, Li J, Liu Y, et al. 2017 Nucl. Fusion 57 102009
Google Scholar
[3] Chen J, Jian X, Chan V, et al. 2017 Plasma Phys. Controlled Fusion 59 075005
Google Scholar
[4] Gorelenkov N N, Pinches S D, Toi K, et al. 2014 Nucl. Fusion 54 125001
Google Scholar
[5] Fasoli A, Gormenzano C, Berk H L, et al. 2007 Nucl. Fusion 47 S267
[6] Pinches S D, Chapman I T, Lauber Ph W, et al. 2015 Phys. Plasmas. 22 021807
Google Scholar
[7] White R B, Rutherford P H, Colestock P, et al. 1988 Phys. Rev. Lett. 60 2038
Google Scholar
[8] Chapman I T 2011 Plasma Phys. Controlled Fusion 53 013001
Google Scholar
[9] Igochine V 2015 Active Control of Magneto-hydrodynamic Instabilities in Hot Plasmas (Berlin: Springer) p259
[10] Poli E, Garcia-Munoz M, Fahrbach H, et al. 2008 Phys. Plasmas 15 032501
Google Scholar
[11] Gobbin M, Marrelli L, Fahrbach H, et al. 2009 Nucl. Fusion 49 095021
Google Scholar
[12] Strumberger E, Gunter S, Schwarz E, et al. 2008 New J. Phys. 10 023017
Google Scholar
[13] Garcia-Munoz M, Fahrbach H, Pinches S D, et al. 2009 Nucl. Fusion 49 085014
Google Scholar
[14] Garcia-Munoz M, Martin P, Fahrbach H, et al. 2007 Nucl. Fusion 47 L10
Google Scholar
[15] Mynick H E 1993 Phys. Fluids B 5 1471
Google Scholar
[16] 郝保龙, 陈伟, 蔡辉山, 等 2020 中国科学: 物理学 力学 天文学 50 065201
Google Scholar
Hao B L, Chen W, Cai H S, et al. 2020 Sci. Sin. Phys. Mech. Astron. 50 065201
Google Scholar
[17] White R B 2014 The theory of toroidally confined plasmas (3th Ed.) (Singapore: World scientific publishing company) p73
[18] Pankin A, McCune D, Andre R, et al. 2004 Computer Physics Communications 159 157
Google Scholar
[19] 高翔, 万宝年, 宋云涛, 等 2019 中国科学: 物理学 力学 天文学 49 045202
Google Scholar
Gao X, Wan B N, Song Y T, et al. 2019 Sci. Sin.-Phys. Mech. Astron. 49 045202
Google Scholar
[20] Yu Q, Gunter S, Scott B D 2003 Phys. Plasmas. 10 798
[21] Wang X J, Yu Q, Zhang X D, et al. 2018 Nucl. Fusion 58 016045
Google Scholar
[22] Hao B L, White R B, Gao X, et al. 2019 Nucl. Fusion 59 076040
Google Scholar
[23] Wu B, Hao B L, White R B, et al. 2017 Plasma Phys. Controlled Fusion 59 025004
Google Scholar
[24] Boozer A H, Kuo-Petravic G 1981 Phys. Fluids 24 851
Google Scholar
[25] Zhao R, Wang Z X, Wang F, et al. 2020 Plasma Phys. Controlled Fusion 62 115001
Google Scholar
[26] Carolipio E M, Heidbrink W W, Forest C B, et al. 2002 Nucl. Fusion 42 853
Google Scholar
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