Abstract—

The results from experimental investigations of chamber internal parts and plasma-facing materials proposed for use in a thermonuclear reactor are reviewed. The thermonuclear reactor internals will experience various heat loads connected with temperature gradients and local exposure dose with the nuclear reaction neutron energy spectrum. The lifetime of the systems will depend on the resistance of materials to neutron and heat loads. Assurance of heat removal is one of serious problems to be solved in implementing a thermonuclear power plant. The components can be cooled either by gas or liquid, including salt solutions and liquid metals. The parameters of coolants, heat-transfer systems, and cooling systems will take values that are still not attainable as of yet. The variety of available design elaborations suggested in the Russian and foreign projects must be substantiated in terms of heat transfer. The parameters of heat and neutron loads will govern the choice of materials for the thermonuclear reactor systems. The international thermonuclear experimental reactor (ITER), which is under construction, will be built using structures, materials, and technologies that have passed the main tests. The ITER cooling systems will operate with forced single-phase convection of turbulent water flow; the heat transfer will be intensified by using inner finning and flow swirling. The thermal protection lining of the plasma-facing chamber’s internal parts in the zones of the highest plasma and heat load will be made of tungsten. In elaborating the design of the next-generation demonstration reactor (DEMO), it will be necessary to additionally develop the blanket construction technologies and solve the problem of converting heat into electricity. The materials for the DEMO reactor must be selected with due regard to the high dose of their irradiation by neutrons with the thermonuclear reaction energy spectrum and critically high heat loads experienced by the plasma-facing chamber’s internals. It will be necessary to develop and test new materials for constructing the DEMO thermonuclear reactor and solve matters concerned with their commercial-scale manufacture.

中文翻译：

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托卡马克热核反应堆的面向等离子体的材料：要求，热稳定性和测试（综述）

摘要-

审查了对用于热核反应堆的腔室内部和面向等离子体的材料进行实验研究的结果。热核反应堆内部将经历与温度梯度和局部暴露剂量以及核反应中子能谱有关的各种热负荷。系统的寿命将取决于材料对中子和热负荷的抵抗力。确保排热是在实施热核电厂中要解决的严重问题之一。组件可以通过气体或液体（包括盐溶液和液态金属）进行冷却。冷却剂，传热系统和冷却系统的参数将采用目前尚无法达到的值。在俄罗斯和国外项目中建议的各种可用的设计细节必须在传热方面得到证实。热负荷和中子负荷的参数将控制热核反应堆系统的材料选择。正在建设中的国际热核实验反应堆（ITER）将使用通过主要测试的结构，材料和技术建造。ITER冷却系统将在湍流强制单相对流的情况下运行；通过使用内部翅片和流动涡流，将增强热传递。等离子体和热负荷最高的区域中，面向等离子体的腔室内部的热保护衬层将由钨制成。在详细设计下一代示范反应堆（DEMO）时，有必要额外开发毯子施工技术，解决热能转化为电能的问题。选择DEMO反应堆的材料时，必须适当考虑中子对它们辐射的高剂量，这些中子具有热核反应能谱，并且必须面对等离子体的腔室内部承受极高的热负荷。有必要开发和测试用于构建DEMO热核反应堆的新材料，并解决与它们的商业规模生产有关的问题。选择DEMO反应堆的材料时，必须适当考虑中子对它们辐射的高剂量，这些中子具有热核反应能谱，并且必须面对等离子体的腔室内部承受极高的热负荷。有必要开发和测试用于构建DEMO热核反应堆的新材料，并解决与它们的商业规模生产有关的问题。选择DEMO反应堆的材料时，必须适当考虑中子对它们辐射的高剂量，这些中子具有热核反应能谱，并且必须面对等离子体的腔室内部承受极高的热负荷。有必要开发和测试用于构建DEMO热核反应堆的新材料，并解决与它们的商业规模生产有关的问题。