Numerical simulation of lower hybrid current drive in CFETR

doi:10.16568/j.0254-6086.202202013

Nuclear Fusion and Plasma Physics ›› 2022, Vol. 42 ›› Issue (2): 250-256.DOI: 10.16568/j.0254-6086.202202013

• Plasma Physics • Previous Articles Next Articles

Numerical simulation of lower hybrid current drive in CFETR

WU Chen-bin1, 2, DING Bo-jiang1, LI Miao-hui1, LI Yong-chun1, 3,WANG Yun-fei1, 2, YAN Guang-hou1, 2, Yves Peysson4

(1. Institute of Plasma Physics, Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031; 2. University of Science and Technology of China, Hefei 230026; 3. Shenzhen University, Shenzhen 518060; 4. CEA, IRFM, Saint-Paul-lez-Durance, 13108, France)

Received:2020-10-20 Revised:2021-12-22 Online:2022-06-15 Published:2022-06-17

CFETR低杂波电流驱动数值模拟研究

吴陈斌1, 2，丁伯江1，李妙辉1，李永春1, 3，王云飞1, 2，闫广厚1, 2，Yves Peysson4

(1. 中国科学院合肥物质科学研究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； 3. 深圳大学，深圳518060； 4. CEA, IRFM, Saint Paul lez Durance, France 13108)

作者简介:吴陈斌(1993-)，男，安徽安庆人，博士研究生，主要从事低杂波电流驱动实验研究。
基金资助:
国家重点研发计划(2016YFA0400603, 2016YFA0400602)；国家自然科学基金(11775259, 11675214, 11805233, 11975266, U19A20113)

Abstract

Abstract: Based on ray tracing code and Fokker-Planck equation code, the dependence of driving current and power deposition position on lower hybrid (LH) wave polar injection position and parallel refractive index spectrum is studied on CFETR. The influence of nonlinear effect of lower hybrid wave at the plasma edge on current driven and power deposition is discussed. An optimized value of LH wave parallel refractive index and injection position is given. The preliminary numerical calculation shows that the nonlinear effect will reduce the driving current in both high field side and low field side, and the difference between high field side and low field side is about 6%, which is less than the difference (~25%) when considering the nonlinear effect.

Key words: Lower hybrid current drive, Parallel refractive index, Polar injection position, CFETR

摘要： 利用射线追踪和福克-普朗克方程，研究了CFETR上驱动电流和功率沉积对低杂波注入位置和耦合波谱的依赖关系，讨论了边界非线性效应对电流驱动与功率沉积的影响，给出了低杂波平行折射率和低杂波注入位置的一个优化值。初步数值计算表明：边界非线性效应会导致驱动电流降低；不考虑低杂波非线性效应时，驱动电流的差异约为6%左右，小于考虑该效应时的差异(~25%)。

关键词: 低杂波电流驱动, 平行波数谱, 极向注入位置, CFETR

CLC Number:

TL62+4

WU Chen-bin, , DING Bo-jiang, LI Miao-hui, LI Yong-chun, , WANG Yun-fei, , YAN Guang-hou, , Yves Peysson. Numerical simulation of lower hybrid current drive in CFETR[J]. Nuclear Fusion and Plasma Physics, 2022, 42(2): 250-256.

吴陈斌, 丁伯江, 李妙辉, 李永春, 王云飞, 闫广厚, Yves Peysson. CFETR低杂波电流驱动数值模拟研究[J]. 核聚变与等离子体物理, 2022, 42(2): 250-256.

References

[1] Zhuang G, Li G Q, Li J, et al. Progress of the CFETR design [J]. Nucl. Fusion, 2019, 59(11): 112010.

[2] Kim S H, Artaud J F, Basiuk V, et al. Lower hybrid assisted plasma current ramp-up in ITER [J]. Plasma Phys. Contr. Fusion, 2009, 51(6): 065020.

[3] Houlberg W A, Gormezano C, Artaud J F, et al. Integrated modelling of the current profile in steady-state and hybrid ITER scenarios [J]. Nucl. Fusion, 2005, 45(11): 1309.

[4] La Haye R J. Neoclassical tearing modes and their control [J]. Phys. Plasmas, 2006, 13(5): 055501.

[5] JPYAD. C3PO, a ray-tracing code for arbitrary axisymmetric magnetic equilibrium [R]. EUR-CEA-FC- 1739, 2008.

[6] Decker J, Peysson Y. DKE: a fast numerical solver for the 3-D relativistic bounce-averaged electron Drift Kinetic Equation [R]. 2004, Corpus ID: 124806501.

[7] Golant V E. Plasma penetration near lower hybrid frequency [J]. Sov Phys Tech Phys-U, 1972, 16(12): 1980.

[8] Bizarro J P, Moreau D. On ray stochasticity during lower-hybrid current drive in tokamaks [J]. Phys. Fluids B: Plasma Physics, 1993, 5(4): 1227.

[9] Decker J, Peysson Y, Hillairet J, et al. Calculations of lower hybrid current drive in ITER [J]. Nucl. Fusion, 2011, 51(7): 073025.

[10] Bonoli P T. Toroidal and scattering effects on lower-hybrid wave propagation [J]. Phys. Fluids, 1982, 25(2): 359−75.

[11] Smick N, Labombard B, Pitcher C S. Plasma profiles and flows in the high-field side scrape-off layer in Alcator C-Mod [J]. J. Nucl. Mater., 2005, 337(1−3): 281.

[12] Castaldo C, Di Siena A, Fedele R, et al. Influence of collisions on parametric instabilities induced by lower hybrid waves in tokamak plasmas [J]. Nucl. Fusion, 2016, 56(1): 016003.

[13] Peysson Y, Decker J, Nilsson E, et al. Advances in modeling of lower hybrid current drive [J]. Plasma Phys. Contr. Fusion, 2016, 58(4): 044008.

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Numerical simulation of lower hybrid current drive in CFETR

CFETR低杂波电流驱动数值模拟研究

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