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The evolution of US helium-cooled blankets

C.P.C. Wong, E.T. Cheng, K.R. Schultz1991年Fusion Engineering and DesignIF 1.7出版社

AbstractThis paper reviews and compares four helium-cooled fusion reactor blanket designs. These designs represent generic configurations of using helium to cool fusion reactor blankets that were studied over the past 20 years in the United States of America (US). These configurations are the pressurized module design, the pressurized tube design, the solid particulate and gas mixture design, and the nested shell design. Among these four designs, the nested shell design, which was invented for the ARIES study, is the simplest in configuration and has the least number of critical issues. Both metallic and ceramic-composite structural materials can be used for this design. It is believed that the nested shell design can be the most suitable blanket configuration for helium-cooled fusion power and experimental reactors.

日本語訳

本论文综述并比较了四种氦冷聚变反应堆包层设计。这些设计代表了在过去20年中于美利坚合众国研究的利用氦冷却聚变反应堆包层的通用构型。这些构型包括加压模块化设计、加压管式设计、固体颗粒与气体混合物设计以及嵌套壳设计。在这四种设计中,为ARIES研究而发明的嵌套壳设计在构型上最为简单,且关键问题最少。金属基和陶瓷基结构材料均可用于该设计。据信,嵌套壳设计可能是最适合氦冷聚变动力堆和实验堆的包层构型。

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