ITER纵场磁体馈线温度场分析

ITER超导托卡马克装置在运行之前要对磁体线圈及馈线系统进行冷却降温,以达到超导体工作所需的低温环境。文中利用大型有限元分析软件ANSYS的温度场分析模块,对纵场磁体馈线系统的降温过程进行模拟仿真,得到了不同时刻馈线上的温度分布情况。在得出冷却过程中馈线上的温度变化之后,又根据稳定状态时的温度分布对结构进行了热应力分析。从而证明了馈线系统冷却方案和结构设计的合理性,为下一步的工作提供了参数依据。

EAST偏滤器V形区域冷却水管的防烧蚀保护

针对EAST前几轮实验中出现的偏滤器DOME板和外靶板间隙区域冷却水管被等离子体烧蚀破坏的问题,提出延伸外靶板石墨瓦结构以扩大打击面积和给冷却水管加装护套两种解决方案,并通过分析确定了具体参数。研究表明,适度的延伸外靶板可有效地防止高能粒子轰击靶板后水管,且对偏滤器区域流导影响不大;采用5mm壁厚高温耐熔钼管护套可有效地保护水管。后一轮的实验结果证明,该方案较好的解决了问题。

等离子体破裂时EAST真空室的电磁和结构分析

用ANSYS有限元软件计算了等离子体破裂时真空室上的涡流、电磁力和应力。有限元模型包含了基本的第一壁部件,以更加准确地研究真空室在瞬态电磁力作用下的结构强度。结果表明,高场侧靶板和内靶板带给真空室较大瞬时应力,但真空室的结构强度仍然满足强度要求。分析可校核和改进第一壁部件的结构设计。

ITER纵场磁体过渡馈线结构力学分析

运用数值方法计算了不同等离子体运行时刻纵场磁体过渡馈线(CFT)超导母线上的电磁载荷,并确定了磁感应强度最大的时刻,采用增量有限元法对过渡馈线进行非线性力学分析,得到不同工况下结构上的应力分布及变形情况。分析结果表明,带有万向节的过渡馈线结构具有足够的强度来承受运行过程中的各种载荷,从而证明了结构设计的合理性。

过冷沸腾数值模拟在EAST第一壁中的应用

介绍了过冷沸腾换热的数值模拟方法以及在EAST第一壁组件冷却系统中的应用。采用双流体模型,系统分析了过冷沸腾壁面换热过程中存在的各种换热模式,给出了Fluent软件封闭关系式中所需的质量、动量以及能量的交换项的形式。采用用户自定义函数(UDF)模拟壁面沸腾气化过程,对提出的模拟方法与已发表的实验数据对比进行了校核,得出合理的结论。最后分析了过冷沸腾两相流在EAST第一壁中的工程应用,模拟了热沉冷却结构的沸腾换热现象。为EAST PFCs的冷却结构优化提供了依据。

ITER纵场磁体超导母线电磁结构分析

阐述了ITER纵场磁体超导母线及其支撑结构设计。运用有限元算法,对工作状态下的超导母线进行电磁结构耦合分析,并对超导母线的应力及变形进行校核,从而验证了纵场磁体超导母线及其支撑结构的安全可靠性,为进一步的详细设计提供了依据。

ITERELM线圈支撑的结构分析与优化设计

ITER ELM线圈的安装位置和工作环境使其在运行中会承受很大的电磁力和受到因核热和欧姆热产生的热膨胀。使用ANSYS有限元软件对六种不同支撑结构做了应力分析,并进行了优化设计。最终确定了当横向梳齿上下两端的通孔为椭圆形且是V字形排列时其最大Tresca应力最小。分析结果为支撑的合理设计提供了理论依据。

Electromagnetic Modeling of the Passive Stabilization Loop at EAST

A passive stabilization loop （PSL） has been designed and manufactured in order to enhance the control of vertical instability and accommodate the new stage for high-performance plasma at EAST. Eddy currents are induced by vertical displacement events （VDEs） and disrup- tion, which can produce a magnetic field to control the vertical instability of the plasma in a short timescale. A finite element model is created and meshed using ANSYS software. Based on the simulation of plasma VDEs and disruption, the distribution and decay curve of the eddy currents on the PSL are obtained. The largest eddy current is 200 kA and the stress is 68 MPa at the outer current bridge, which is the weakest point of the PSL because of the eddy currents and the magnetic fields. The analysis results provide the supporting data for the structural design.

Optimization and Update of EAST In-Vessel Components in 2011

For safe operation with active water cooling plasma facing components （PFCs） to handle a large input power over a long pulse discharge, some design optimization, R＆D and maintenance were accomplished to improve the in-vessel components. For the purpose of large plasma current （1 MA） operation, the previous separated top and bottom passive stabilizers in the low field were electrical connected to stabilize plasma in the case of vertical displace events （VDEs）. The design and experiments are described in this paper

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Static Structural Analysis for a Neutron Shielding Block in ITER

The ITER neutron shielding blocks are located between the outer shell and the inner shell of the vacuum vessel to provide neutron shielding. Considering the combined loads acting on the shielding blocks during ITER plasma operation, the structure of the shielding blocks must be evaluated. Using the finite element method with ANSYS analysis software, static structural analysis is performed, including elastic analysis and limit analysis for one typical shielding block. The evaluated results based on RCC-MR code show that the structure of this shielding block can meet the design requirement.

Design of Tokamak ELM Coil Support in High Nuclear Heat Environment

In Tokomak, the support of the ELM coil, which is close to the plasma and subject to high radiation level, high temperature and high magnetic field, is used to transport and bear the thermal load due to thermal expansion and the alternating electromagnetic force generated by high magnetic field and AC current in the coil. According to the feature of ITER ELM coil, the mechanical performance of rigid and flexible supports under different high nuclear heat levels is studied. Results show that flexible supports have more excellent performance in high nuclear heat condition than rigid supports. Concerning thermal and electromagnetic （EM） loads, optimized results further prove that flexible supports have better mechanical performance than rigid ones. Through these studies, reasonable support design can be provided for the ELM coils or similar coils in Tokamak based on the nuclear heat level.

Mechanical Analysis and Optimization of ITER Upper ELM Coil & Feeder

International thermonuclear experimental reactor （ITER） edge localized mode （ELM） coils are used to mitigate or suppress ELMs. The location of the coils in the vacuum vessel and behind the blankets exposes them to high radiation levels and high temperatures. The feeders provide the power and cooling water for ELM coils. They are located in the chinmey ports and experience lower radiation and temperature levels. These coils and feeders work in a high magnetic field environment and are subjected to alternating electromagnetic force due to the interaction between high magnetic field and alternating current （AC） current in the coils. They are also subjected to thermal stresses due to thermal expansion. Using the ITER upper ELM coil and feeder as an example, mechanical analyses are performed to verify and optimize the updated design to enhance their structural performance. The results show that the conductor, jacket and bracket can meet the static, fatigue and crack threshold criteria. The optimization indicates that adding chamfers to the bracket can reduce the high stress of the bracket, and removing two rails can reduce the peak reaction force on the two rails arising from thermal expansion.

Rapid Thermal-Hydraulic Analysis and Design Optimization of ITER Upper ELM Coils

ITER edge localized mode （ELM） coils are important components of the in-vessel coils （IVCs） and they are designed for mitigating or suppressing ELMs. The coils located on the vacuum vessel （VV） and behind the blanket are subjected to high temperature due to the nuclear heat from the plasma, the Ohmic heat induced by the working current and the thermal radiation from the environment. The water serves as coolant to remove the heat deposited into the coils. Based on the results of nuclear analysis, the thermal-hydraulic analysis is performed for the preliminary design of upper ELM coils using a rapid evaluation method based on 1D treatment. The thermal-hydraulic design and operating parameters including the water flow velocity are optimized. It is found that the rapid evaluation method based on 1D treatment is feasible and reliable. According to the rapid analysis method, the thermal hydraulic parameters of two water flow schemes are computed and proved similar to each other, providing an effective basis for the coil design. Finally, considering jointly the pressure drop requirement and the cooling capacity, the flow velocity is optimized to 5 m/s.

Optimization of Heat-Sink Cooling Structure in EAST with Hydraulic Expansion Technique

Considering utilization of the original chromium-bronze material, two processing techniques including hydraulic expansion and high temperature vacuum welding were proposed for the optimization of heat-sink structure in EAST. The heat transfer performance of heat-sink with or without cooling tube was calculated and different types of connection between tube and heat-sink were compared by conducting a special test. It is shown from numerical analysis that the diameter of heat-sink channel can be reduced from 12 mm to 10 mm. Compared with the original sample, the thermal contact resistance between tube and heat-sink for welding sample can reduce the heat transfer performance by 10%, while by 20% for the hydraulic expansion sample. However, the welding technique is more complicated and expensive than hydraulic expansion technique. Both the processing technique and the heat transfer performance of heat-sink prototype should be further considered for the optimization of heat-sink structure in EAST.

Physical design of a new set of high poloidal mode number coils in the EAST tokamak

An external resonant magnetic perturbation(RMP)field,which is an effective method to mitigate or suppress the edge localized mode(ELM),has been planned to be applied on the ELM control issue in ITER.A new set of magnetic perturbation coils,named as high m coils,has been developed for the EAST tokamak.The magnetic perturbation field of the high m coils is localized in the midplane of the low field side,with the spectral characteristic of high m and wide n,where m and n are the poloidal and toroidal mode numbers,respectively.The high m coils generate a strong localized perturbation field.Edge magnetic topology under the application of high m coils should have either a small or no stochastic region.With the combination of the high m coils and the current RMP coils in the EAST,flexible working scenarios of the magnetic perturbation field are available,which is beneficial for ELM control exploration on EAST.Numerical simulations have been carried out to characterize the high m coil system,including the magnetic spectrum and magnetic topology,which shows a great flexibility of magnetic perturbation variation as a tool to investigate the interaction between ELM and external magnetic perturbation.

Electromagnetic–thermal–structural coupling analysis of the ITER edge localized mode coil with flexible supports

In a fusion reactor, the edge localized mode（ELM） coil has a mitigating effect on the ELMs of the plasma. The coil is placed close to the plasma between the vacuum vessel and the blanket to reduce its design power and improve its mitigating ability. The coil works in a high-temperature,high-nuclear-heat and high-magnetic-field environment. Due to the existence of outer superconducting coils, the coil is subjected to an alternating electromagnetic force induced by its own alternating current and the outer magnetic field. The design goal for the ELM coil is to maintain its structural integrity in the multi-physical field. Taking as an example the middle ELM coil（with flexible supports） of ITER（the International Thermonuclear Fusion Reactor）, an electromagnetic–thermal–structural coupling analysis is carried out using ANSYS. The results show that the flexible supports help the three-layer casing meet the static and fatigue design requirements. The structural design of the middle ELM coil is reasonable and feasible. The work described in this paper provides the theoretical basis and method for ELM coil design.