The Central Solenoid Model Coil (CSMC) has been manufactured and assembled as part of the R&D projects for the China Fusion Engineering Test Reactor (CFETR), and will be tested at ASIPP. The measurement of the current sharing temperature (T-cs) of the coil at maximum operating current of 47.65 kA is proposed to assess the performance of the coil. The T-cs is defined as the point where the electric field locally reaches 10 mu V/m. During the T-cs test, voltage taps measure the voltage of each cooling channel of the CSMC. Reliable thermal-hydraulic predictions are necessary to estimate the total voltage across a cooling channel when the local electric field is 10 mu V/m, supporting the definition of the T-cs loop heating strategy. A predictive analysis of the T-cs tests for the CSMC is carried out, using the GANDALF code. An optimum heating scenario, based on the staircase strategy is developed to reduce cryogenic costs.

The Central Solenoid Model Coil (CSMC) has been manufactured as part of the R&D projects for the China Fusion Engineering Test Reactor (CFETR), and it will undergo testing in the second half of 2024. For the safety operation of magnet, predictive analyses are required to study thermal-hydraulic behavior of the CSMC during the quench. In this paper, the different quench initial position is detailed studied, for example, quench initiates at the peak magnetic field region and the lowest magnetic field region. In addition, the different quench disturbances are considered, such as (disturber length 0.01 m and disturber time 3 ms), (disturber length 1 m and disturber time 3 ms), and (disturber length 6 m and disturber time 100 ms). In all cases, the designed quench protection system is satisfied with the present design criteria concerning the hot spot temperature and the maximum helium pressure.

The toroidal field (TF) coil is a crucial system in China Fusion Engineering Test Reactor (CFETR). The operating safety of the magnet will strongly depend on the heat load and the capability of the coolant to remove it. The adequate cooling design of the TF coil case can effectively establish thermal shielding to prevent the heat flux from the TF coil case to the winding. An orthogonal scheme is applied to optimize the cooling design. The effect of the parameters of the cooling channels on the heat transfer from case to conductors is studied, such as the channel numbers N, the distance between the cooling channel and the edge P, the diameter of the pipe D, and the mass flow rate M. Compared with the original design, the optimization design significantly improves the cooling capacity.

China Fusion Engineering Test Reactor (CFETR) has received much attention over the past several years, aiming at bridging the gap between the International Thermonuclear Experimental Reactor (ITER) and the Demonstration Fusion Reactor (DEMO). The toroidal field (TF) coils play an important role in the tokamak, which provide the main magnetic field to confine the plasma. In order to evaluate the feasibility of superconducting magnets used in CFETR, it is important to predict the magnet performance in terms of temperature margin during normal operation conditions. The simulations confirm the need to increase the mass flow rate, or decrease the hydraulic length of high field windings. The results show that the proposed reduction of hydraulic length is more effective to increase the minimum temperature margin.

The toroidal field (TF) coil is a crucial system in the tokamak, which provides the main magnetic field to confine the plasma. One TF coil of the China Fusion Engineering Test Reactor (CFETR) will be constructed with the support of the Chinese government in the next five years. In order to study the quench behavior of the CFETR TF coil, the assumed quench initiation at the maximum and minimum temperature margin position of the TF coil is analyzed, and the effect of the quench detection threshold on the hot spot temperature is studied. It is found that 0.5 V quench detection voltage leads to hot spot temperature above 250 K in the low-field region. In order to meet the design criteria of the hot spot temperature, the quench detection voltage should be less than 0.2 V.

中国聚变工程实验堆(CFETR)是中国新一代聚变装置,环向场(TF)磁体系统是托卡马克关键部件之一.根据TF线圈冷却要求,给出CFETR TF线圈盒冷却的初步设计.通过开展2D模拟分析TF线圈盒冷却通道数量、质量流量、位置等参数对冷却效果的影响.模拟结果表明,增加冷却通道数量可显著减少导体热流量;而增加质量流量对冷却效果的提高不明显.线圈盒内腿段盖板(AP)组件冷却通道由16条增加至30条后,绕组热流量降低至2.01 W/m,减小了约37％.同时,模拟发现缩短冷却通道与拐角间的距离,可显著提升冷却效果.