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1. CFETR 等离子体平衡计算 的一些 相关 问题 2. CFETR 电流驱动的初步讨论

1. CFETR 等离子体平衡计算 的一些 相关 问题 2. CFETR 电流驱动的初步讨论. CFETR 等离子体平衡计算的 一些相关问题. 李国强 钱金平 郭勇 罗 正 平 任启龙 吴斌 肖炳甲 邢哲 万宝年 中科院等离子体物理研究所. 等离子体电流. Ip 是堆芯等离子体性能的关键参数之一 x x ITER reference scenarios. CFETR 的不同参数下的 Ip. q profile of CFETR r eference scenarios Inductive: q0~1 , q95 ≥3

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1. CFETR 等离子体平衡计算 的一些 相关 问题 2. CFETR 电流驱动的初步讨论

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  1. 1. CFETR等离子体平衡计算的一些相关问题2. CFETR电流驱动的初步讨论

  2. CFETR等离子体平衡计算的一些相关问题 李国强 钱金平 郭勇 罗正平 任启龙 吴斌 肖炳甲 邢哲万宝年 中科院等离子体物理研究所

  3. 等离子体电流 • Ip是堆芯等离子体性能的关键参数之一 • x • x • ITER reference scenarios

  4. CFETR的不同参数下的Ip • q profile of CFETR reference scenarios • Inductive: q0~1, q95 ≥3 • Hybrid: q0≥1, q95=3.9, flat central q • Steady-state: q0=2.3, q95=5.0, qmin=1.8 • Ip of CFETR at different scenario and Bt0 Hybrid Steady-state inductive

  5. CS/PF线圈和等离子体平衡位形 • ITER-like plasma shape • R=5.5m, a=1.6m • k= 1.85 • δu=0.42, δl=0.52 • Bt0=5.3T, Ip=10MA • q95=3.1, li(3) =0.80 • V=470m3, S=487m2

  6. PF coils size and position

  7. VS needed for CFETR 10MA conductive scenario • Vs needed for fully inductive ramp-up • 阻性消耗：μ*Ip*R0*C_Ejima = 31 VS • 感性消耗：μ*Ip*R0*li(3)/2 = 28 VS • 外部伏秒消耗Lext*Ip=μ*Ip*R0*[ln(8*R0/a)-2]~ 87 VS • 总共需要大约 ~150 Vs • Break down: ~10 Vs (ITER) • Flat top：30 Vs ? • Ramp-down:? • 总共需要大约 180~190 Vs

  8. Time evolution of CFETR 10MA inductive ramp-up

  9. PF coils current at different flux state (10MA) Flux state 83Wb 75Wb -70Wb -100Wb limit PF1 17.422 16.310 9.222 3.146 21.8 PF2 5.115 4.935 11.386 11.053 8.8 PF3 -1.726 -1.478 -14.277 -14.532 11.5 PF4 -1.272 -1.875 -17.385 -17.719 11.5 PF5 4.351 5.662 12.388 11.781 8.8 PF6 16.700 17.114 20.606 15.881 21.8 CS3L 18.088 16.558 12.665 4.394 16.8 CS2L 19.963 20.352 -11.259 -22.106 16.8 CS1L 20.671 20.164 -14.572 -20.479 16.8 CS1U 20.568 20.361 -16.050 -21.1916.8 CS2U 19.394 20.971 -6.9781 -19.47 16.8 CS3U 17.429 17.083 -1.7082 -7.381 16.8

  10. PF coils current at different flux state (8MA) Flux state 45Wb -60Wb -80Wb PF1 9.774 6.030 1.778 21.8 PF2 2.899 10.794 10.560 8.8 PF3 -0.733 -12.271 -12.408 11.5 PF4 -1.031 -13.956 -14.280 11.5 PF5 3.297 9.025 9.148 8.8 PF6 10.247 19.219 14.884 21.8 CS3L 9.633 4.409 -0.757 16.8 CS2L 11.879 -7.033 -14.167 16.8 CS1L 12.051 -13.058 -16.781 16.8 CS1U 12.215 -12.261 -16.559 16.8 CS2U 12.302 -8.065 -15.392 16.8 CS3U 9.940 -2.592 -6.631 16.8

  11. Divertor configuration • ITER-like divertor • Super-X • Snowflake • 还未找到super-X和snowflake的合理解 Super-X ITER-like Snowflake

  12. Profiles of equilibria of CFETR inductive scenario • Profiles are key issue for core plasma parameter • Pressure and q profile are from DIII-D ITER demonstration shot 136345 • At the edge region, the bootstrap current aligns with the total current Pressure q

  13. Pedestal height and width • Pedestal height is a key element for fusion power • Pedestal height and width can be calculated by the EPED1 model (PB mode and KBM) • With EPED1 model, ITER SS scenario only has 140MW fusion power • We will use EPED1 model to confirm the pedestal height and width of CFETR

  14. Discussion • Still a lot work to do for CFETR equilibria configuration • Plasma shape? Squareness may increase the Ip • Reduce the minor radius? • PF coils number? size and position? • Divertor configuration • Pedestal height and width

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