He-cooled divertor development for DEMO
He-cooled divertor development for DEMO
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DOI：
10.1016/j.fusengdes.2007.05.027
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发表时间：
2007-10
期刊：
影响因子：
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通讯作者：
P. Norajitra;R. Giniyatulin;T. Ihli;G. Janeschitz;W. Krauss;R. Krüssmann;V. Kuznetsov;I. Mazul;V. Widak;I. Ovchinnikov;R. Ruprecht;B. Zeep
中科院分区：
文献类型：
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作者：
P. Norajitra;R. Giniyatulin;T. Ihli;G. Janeschitz;W. Krauss;R. Krüssmann;V. Kuznetsov;I. Mazul;V. Widak;I. Ovchinnikov;R. Ruprecht;B. Zeep
未来核聚变电厂的氦冷导流器发展的目标是抵抗至少10MW/m2的高热流。发展包括设计、分析和实验领域。提出了一种基于射流冲击冷却的氦冷却模块化射流概念（HEMJ）作为参考方案。在与Efremov研究所的合作下，工作的目的是建造和高热流密度钨原型模型，以证明其可制造性和性能。为此，建立了一个氦气环，以模拟接近DEMO （10MPa He, 600°C）的实际热工条件。首次高热流密度试验结果证实了该导流器设计的可行性和性能。
Goal of the He-cooled divertor development for future fusion power plants is to resist a high heat flux of at least 10MW/m2. The development includes the fields of design, analyses, and experiments. A helium-cooled modular jet concept (HEMJ) has been defined as reference solution, which is based on jet impingement cooling. In cooperation with the Efremov Institute, work was aimed at construction and high heat flux tests of prototypical tungsten mockups to demonstrate their manufacturability and their performances. A helium loop was built for this purpose to simulate the realistic thermo-hydraulics conditions close to those of DEMO (10MPa He, 600°C). The first high heat flux test results confirm the feasibility and the performance of the divertor design.