摘要：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。

摘要：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。

摘要：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。

摘要：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。

摘要：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。

摘要：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.

摘要：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.