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Design and manufacture of the fuel element for the 10 MW high temperature gas-cooled reactor

机译:10 MW高温气冷堆燃料元件的设计与制造

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The Chinese 10 MW high temperature gas-cooled reactor (HTR-10) attained its first criticality on December 21, 2000. The fabrication of the first fuel for the HTR-10 started in February 2000 at the Institute of Nuclear Energy Technology (INET), Tsinghua University. Up to September 2000, a total of 11721 spherical fuel elements were successfully produced. The average free uranium fraction of the first fuel-determined by the burn-leach method-was 5.0*10~-5. So far, the release rate R/B of the fission gas, measured in the irradiation test, shows that not a single particle in three irradiated spherical fuel elements failed as the results of the irradiation test carried out in Russia. This paper describes the design parameter, the fabrication technology and the performance data of the HTR-10 first fuel, and the production and quality control experiences obtained from the manufacture of the first fuel for the HTR-10.
机译:中国的10兆瓦高温气冷堆(HTR-10)于2000年12月21日达到了第一个临界点。HTR-10的第一种燃料于2000年2月在核能技术研究所(INET)开始制造。 ,清华大学。截至2000年9月,共成功生产了11721个球形燃料元件。通过燃烧-浸出法确定的第一种燃料的平均游离铀分数为5.0 * 10〜-5。到目前为止,在辐射试验中测得的裂变气体的释放速率R / B表明,在俄罗斯进行的辐射试验结果表明,三种辐照的球形燃料元件中没有一个颗粒失败。本文介绍了HTR-10第一燃料的设计参数,制造技术和性能数据,以及从HTR-10第一燃料的制造获得的生产和质量控制经验。

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