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介绍了EAST超导托卡马克偏滤器的最新冷却模块结构。利用FLUENT有限元软件对不同参数下的模型进行了稳态热分析,定量研究了冷却模块换热能力随各参数的变化规律。针对EAST装置给出了初步优化的参数范围,为水冷钨铜偏滤器的设计制造提供了参考。这对于托卡马克装置及聚变堆偏滤器研究具有十分重要的意义。     

EAST 钨偏滤器外靶板热工水力分析

为提高EAST 偏滤器的抗热载和排热能力,将偏滤器第一壁的材料由原来的石墨改为钨,在结构上,靶板采用了类ITER 的单块结构,支撑和冷却采用一体化的盒式结构。确定了EAST 钨偏滤器的冷却结构后,通过水管的流固耦合传热模型,分析了外靶板在紊流冷却方式下的散热情况。同时计算了在水冷系统失效的情况下,偏滤器外靶板的危险区域在3、5、8、10MW·m^-2 热流密度下的瞬态温度分布情况。结果表明,水流速度在4m·s^-1 时, 水管可以承受峰值功率10MW·m^-2 的热流密度,能够很好地满足EAST 装置运行的排热要求。     

基于EAST装置量热系统的 第一壁热负荷实验研究

通过测量EAST装置水冷系统的出入口冷却水的温差和流量，搭建了第一壁热负荷测量系统，实现了第一壁热负荷的分布测量。实验结果表明，在上单零偏滤器位形放电实验中，该系统测量的热负荷约占总注入能量的80%，其中，接近50%的热负荷沉积在上偏滤器区域。高的加热功率会使得第一壁热负荷更快上升。通过冷却水降温曲线拟合计算得出EAST装置上钨偏滤器水冷系统的热衰减时间约为下石墨偏滤器水冷系统的十分之一。     

EAST位形磁流体平衡的模拟

对托卡马克平衡反演数值计算代码EFIT进行了改进,使之适用于EAST装置的磁流体平衡研究.用改进后的平衡反演代码EFIT模拟了EAST装置稳态阶段的偏滤器平衡位形.提出极向场线圈电流作为线性方程组主约束条件,期望位形作为从约束条件,求解非对称电流条件下自由边界平衡问题的方法.结果表明,该方法能较为容易地得到非对称电流条件产生的平衡位形,在非对称电流条件下自由边界平衡计算是收敛的.     

CFETR氦冷偏滤器初步设计与分析

基于中国聚变工程试验堆(CFETR)偏滤器位形,初步设计了指状、平板和 T 形三种氦冷偏滤器模型, 在 10MPa 入口氦压力、10MW⋅m⁻² 稳态热负荷下,分别对其进行传热数值分析。通过优化结构设计和氦入口参数, 降低了靶板工作温度,探索了三种单元结构靶板处理高热负载的能力。在 20MW⋅m⁻² 的稳态热负荷下,对优化后 的 T 形和指状单元结构进行了受热分析,并由此提出了混合型 CFETR 氦冷偏滤器初步结构。      

多喷嘴氦冷偏滤器的优化与分析

利用ANSYS/CFX对聚变堆氦冷多喷嘴冷却偏滤器模块在相同高热负荷条件但不同冷却条件下进行了有限元数值分析,得到了偏滤器冷却单元的温度和换热系数分布图,将该温度场作为结构力学分析的加载条件,利用ANSYS/Mechanical对冷却模块进行了稳态条件下的结构应力分析,得到了具有不同结构参数的偏滤器模块的应力分布。通过分析各结构参数对偏滤器模型的热应力的影响,对结构参数进行筛选,得到内应力相对较低的结构设计,从而优化多喷嘴氦冷偏滤器结构。     

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利用ANSYS/CFX对聚变堆氦冷多喷嘴冷却偏滤器模块在相同高热负荷条件但不同冷却条件下进行了有限元数值分析,得到了偏滤器冷却单元的温度和换热系数分布图,将该温度场作为结构力学分析的加载条件,利用ANSYS/Mechanical对冷却模块进行了稳态条件下的结构应力分析,得到了具有不同结构参数的偏滤器模块的应力分布.通过分析各结构参数对偏滤器模型的热应力的影响,对结构参数进行筛选,得到内应力相对较低的结构设计,从而优化多喷嘴氦冷偏滤器结构.     

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利用EAST装置单道远红外HCN激光干涉仪测量了等离子体中心道(R=1.82m)线平均电子密度。通过充气加料连续提升主等离子体密度,首次在EAST装置上观察到偏滤器等离子体的三种不同状态：低再循环(偏滤器靶板处等离子体温度较高,密度较低),高再循环(偏滤器靶板处等离子体温度较低,密度较高)和脱靶(偏滤器靶板处等离子体温度和密度都很低)等离子体状态。分析了EAST偏滤器在这三种不同状态下的物理现象。     

EAST远红外激光干涉仪与密度爬升实验研究

利用EAST装置单道远红外HCN激光干涉仪测量了等离子体中心道(R=1.82m)线平均电子密度。通过充气加料连续提升主等离子体密度,首次在EAST装置上观察到偏滤器等离子体的三种不同状态：低再循环(偏滤器靶板处等离子体温度较高,密度较低),高再循环(偏滤器靶板处等离子体温度较低,密度较高)和脱靶(偏滤器靶板处等离子体温度和密度都很低)等离子体状态。分析了EAST偏滤器在这三种不同状态下的物理现象。     

晕电流作用下EAST上偏滤器靶板的可靠性研究

通过建立晕电流峰值分布的高斯混合模型,结合靶板结构的极限状态方程,利用Monte Carlo 方法开展了晕电流作用下EAST 上偏滤器靶板的可靠性研究。研究结果表明,在晕电流作用下,EAST 上偏滤器靶板具有极高的可靠性。这一结果为EAST 上偏滤器以及CFETR 的可靠性研究提供了参考。     

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In order to improve the anti-thermal load and heat dissipation performance of the divertor of EAST, its first wall material is changed to tungsten from graphite. In the structure, outer target adopts the ITER-like monoblock, bracing and cooling structure adopts incorporate cassette. After establishing the cooling structure of EAST tungsten divertor, the flows-solid coupling heat conduction model of water-pipes is used to analyze the heat dissipation situation of outside target in the form of turbulent flow. While the cooling system comes to failure, a series of heat flux value 3MW·m^-2, 5MW·m^-2, 8MW·m^-2, 10MW·m^-2 are applied in the hazardous area to analyze transient conditions and real temperature distribution. The results shows that if the water flows at 4m·s^-1, the cooling pipes can withstand the heat flux with peak power in 10MW·m^-2. It can well meet the needs in heat dissipation of EAST experiment.     

Study on divertor plasma behavior through sweeping strike point in new lower divertor on EAST

A series of L-mode discharges have been conducted in the new ‘corner slot’ divertor on the Experimental Advanced Superconducting Tokamak (EAST) to study the divertor plasma behavior through sweeping strike point. The plasma control system controls the strike point sweeping from the horizontal target to the vertical target through poloidal field coils, with keeping the main plasma stability. The surface temperature of the divertor target cools down as the strike point moves away, indicating that sweeping strike point mitigates the heat load. To avoid the negative effect of probe tip damage, a method based on sweeping strike point is used to get the normalized profile and study the decay length of particle and heat flux on the divertor target λ_js, λ_q. In the discharges with high radio-frequency (RF) heating power, electron temperature T_e is lower and λ_js is larger when the strike point locates on the horizontal target compared to the vertical target, probably due to the corner effect. In the Ohmic discharges, λ_js, λ_q are much larger compared to the discharges with high RF heating power, which may be attributed to lower edge T_e.     

EAST 第一壁水冷结构类型传热能力的比较分析

为了能够更加直接地比较EAST 中第一壁水冷结构的传热能力，给出在未来设计中的选型参考，利用模拟分析的手段对现有的以及正在研制的水冷结构进行了在相同的工况下传热能力的对比分析。通过比较水冷结构中不同材料的温度，得到传热能力的优劣，同时考虑各种材料的许用温度，结合工艺难度及工程造价等因素对各结构进行了整体比较。计算结果显示，就传热能力而言，钨串结构最好，焊接结构次之，螺栓连接结构最差。结合造价及工艺难度等条件可以看出，钨串结构仍是目前最适用于高热负荷区域的结构，W/TZM/C 作为第一壁材料的焊接结构适用于较低热负荷的区域，螺栓连接结构在未来发展中将会逐渐被取代。     

聚变堆熔盐冷却偏滤器靶板结构设计与分析

为提高偏滤器的抗中子辐照能力,兼顾高热承载能力和聚变堆经济性的需要,提出了基于熔盐冷却(MSC)的偏滤器靶板结构设计。它采用FLiNaK作为冷却剂,钨镧合金为热沉材料,钨为第一壁材料。通过数值计算评估了靶板的热负荷承载能力,并完成了偏滤器冷却剂回路设计,优化了偏滤器各模块之间的流量分配。此MSC偏滤器靶板设计可以有效去除10~15MW•m^-2热负荷,为适应未来聚变堆偏滤器靶板发展的需要提供了一种设计解决方案。     

L–H power threshold studies with tungsten/carbon divertor on the EAST tokamak

The power threshold for low (L) to high (H) confinement mode transition achieved by radio-frequency heating and molybdenum first wall with lithium coating has been experimentally investigated on the EAST tokamak for two sets of divertor geometries and materials: tungsten/carbon divertor and full carbon divertor. For both sets of divertors, the power threshold was found to decrease with gradual accumulation of the lithium wall coating, suggesting the important role played by the low Z impurities and/or the edge neutral density on the L–H power threshold. When operating in the upper single null configuration, with the ion grad-B drift direction away from the primary X-point, a lower normalized power threshold is observed in EAST with the tungsten/carbon divertor, compared to the carbon divertor after intensive lithium wall coating. A newly installed cryopump increasing the pumping efficiency also plays an important part in the observed lower threshold. In addition, the H-mode in the Quasi-Snowflake divertor configuration has been obtained on EAST, exhibiting higher L–H power threshold compared to the lower single null configuration with similar I_P/B_T pairs.     

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介绍了EAST超导托卡马克偏滤器的结构和相关分析,并对第一壁材料的导热性能和结构的换热效果进行了实验测试,验证了结构的可靠性。     

Heat Flux on EAST Divertor Plate in H-mode with LHCD/LHCD+NBI

Based on the surface temperature measured by the infrared camera on the experimental advanced superconducting tokamak(EAST), the heat fluxes on the lower outer divertor target plate during H-mode with the lower-hybrid wave current drive(LHCD) only and with the LHCD combined with the neutral beam injection(NBI) are calculated by the DFLUX code and compared. The analyzed discharges are lower single null divertor configuration discharges. In the case with the LHCD only(I_p~400 kA, P_(LHCD)~2 MW), ELM-free appears after L-H transition with the peak heat flux on the lower outer target plate less than 1 MW/m2. However, there is no ELMfree appearing after the L-H transition in the case with the LHCD+NBI(I_P~300 kA, P_(LHCD)+P_(NBI)~2 MW).The results show that the peak heat fluxes on the lower outer target plate in the LHCD+NBI H-mode cases are larger than those in the LHCD H-mode under the similar auxiliary heating power. This is because the heat flux profiles of the lower outer target plate as a function of plate location in ELMing with the LHCD+NBI are narrower than those with the LHCD only. The results are consistent with the results in terms of the scrape-off layer width observed in the EAST.     

Radiative divertor behavior and physics in Ar seeded plasma on EAST

To investigate the radiative divertor behavior and physics for the scenario of impurity seeded plasma in ITER, the radiative divertor experiments with argon(Ar) seeding under ITER-like tungsten divertor condition were carried out during recent EAST campaigns. The experimental results reveal the high efficiency of reducing heat load and particle flux onto the divertor targets owing to increased radiation by Ar seeding. We achieve detached plasmas in these experiments. The inner–outer divertor asymmetry reduces after Ar seeding. Impurities, such as Ar, C, Li, and W, exist in the entire space of the vacuum chamber during EAST operations, and play important roles in power exhausting and accelerating the plasma detachment process. It is remarkable that the contamination of the core plasma is observed using Ar seeding owing to the sputtering of plasma facing components(PFCs), particularly when Ar impurity is injected from the upper tungsten divertor.