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Influence of graphitization degree of nuclear graphite on HTGR reactor physics calculation
Annals of Nuclear Energy ( IF 1.9 ) Pub Date : 2020-08-01 , DOI: 10.1016/j.anucene.2020.107458
Lerui Zhang , Ding She , Lei Shi

Abstract Nuclear graphite is widely used in traditional and advanced nuclear reactors. Especially in High Temperature Gas-cooled Reactors (HTGRs), nuclear graphite is the main composition of fuel element and reflector. The graphite cross section data libraries used in practical reactor physics calculations are generally evaluated from ideal single crystal graphite material. However, the actual nuclear graphite is not ideal but contains a certain proportion of amorphous carbon, which is measured as graphitization degree. By this short paper, it is shown that the graphitization degree of nuclear graphite has a considerable influence on HTGR reactor physics calculation. The observation would be important for the engineering design of various types of graphite reactors.

中文翻译:

核石墨石墨化程度对高温气冷堆反应堆物理计算的影响

摘要 核石墨广泛用于传统和先进的核反应堆。特别是在高温气冷堆 (HTGR) 中,核石墨是燃料元件和反射器的主要成分。实际反应堆物理计算中使用的石墨横截面数据库通常是从理想的单晶石墨材料中评估的。然而,实际的核石墨并不理想,而是含有一定比例的无定形碳,以石墨化程度来衡量。这篇短文表明,核石墨的石墨化程度对HTGR反应堆物理计算有相当大的影响。该观察结果对于各种类型石墨反应堆的工程设计具有重要意义。
更新日期:2020-08-01
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