L-H和H-L跃迁对托卡马克反应堆运行的影响

Y. Gott, E. Yurchenko
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摘要

考虑了L-H和H-L跃迁对托卡马克反应堆运行的影响。在总环向电流恒定的情况下,两种初始模态都被认为是具有相同热能的准平衡态。已经开发了一种量化托卡马克反应堆在这些跃迁期间中子产率变化的方法,这些跃迁发生的时间远远短于等离子体能量约束时间。该方法基于对Grad-Shafranov方程解的对偶性的利用。该方程中包含的任意函数是将归一化等离子体压力分布与在DIII-D设备上获得的径向流坐标进行近似的结果。为了计算L-H和后H-L跃迁过程中中子通量的变化,我们将这些等离子体压力分布用于ITER装置参数的笛卡尔坐标表示。数值计算表明,在后H-L跃迁中,整体中子产量可能出现一个大的峰值,这是以前在实验中发现的(ALCATOR-C-Mode, 2001)。由于在托卡马克反应堆ITER运行期间中子通量的这种增加对人员和设施本身都构成严重威胁,因此有必要排除这种转变的可能性。因此,有必要开发这样一种反应堆设计,使其有可能在l模式操作中获得自我维持的热核反应。
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Effect of L-H and H-L Transitions on Tokamak-reactor Operation
The effect of L-H and H-L transitions on the tokamak-reactor operation is considered. Both initial modes are considered as quasi-equilibrium states with the same thermal energy for constant total toroidal currents. A method has been developed for quantification the change in neutron yield in a tokamak- reactor during these transitions occurring over times much shorter than the plasma energy confinement time. The method is based on the use of duality of solutions of the Grad-Shafranov equation. The arbitrary functions included in this equation were found as a result of approximation of the normalized plasma pressure profiles, presented versus on the radial flow coordinate obtained at the DIII-D facility. To calculate changes in neutron fluxes during L-H and back H-L transitions, we used these plasma pressure distributions for the ITER device parameters presented in Cartesian coordinates. A numerical calculation showed that in the back H-L transition, a large spike on the global neutron production is possible, which was previously discovered experimentally (ALCATOR-C-Mode, 2001). Since such an increase in neutron fluxes during tokamak-reactor ITER operation poses a serious threat to both the personnel and the facility itself, it is necessary to exclude the possibility of such transitions. Thus, it is necessary to develop such a reactor design that would make it possible to obtain a self-sustaining thermonuclear reaction in the L-mode operation.
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