Kenzhina Inesh, Blynskiy Petr, Kozlovskiy Artem, Begentayev Meiram, Askerbekov Saulet, Zaurbekova Zhanna, Tolenova Aktolkyn
Laboratory of Structural Materials for Nuclear Power Plants, Al-Farabi Kazakh National University, Almaty 050032, Kazakhstan.
Advanced Electronics Development Laboratory, Kazakh-British Technical University, 59 Tole bi St., Almaty 050000, Kazakhstan.
Materials (Basel). 2022 Jul 6;15(14):4741. doi: 10.3390/ma15144741.
The purpose of this work is to characterize the morphological, structural, and strength properties of model prototypes of new-generation TRi-structural ISOtropic particle fuel (TRISO) designed for Generation IV high-temperature gas reactors (HTGR-type). The choice of model structures consisting of inner pyrolytic carbon (I-PyC), silicon carbide (SiC), and outer pyrolytic carbon (O-PyC) as objects of research is motivated by their potential use in creating a new generation of fuel for high-temperature nuclear reactors. To fully assess their full functional value, it is necessary to understand the mechanisms of resistance to external influences, including mechanical, as in the process of operation there may be external factors associated with deformation and leading to the destruction of the surface of fuel structures, which will critically affect the service life. The objective of these studies is to obtain new data on the fuel properties, as well as their resistance to external influences arising from mechanical friction. Such studies are necessary for further tests of this fuel on corrosion and irradiation resistance, as closely as possible to real conditions in the reactor. The research revealed that the study samples have a high degree of resistance to external mechanical influences, due to the high strength of the upper layer consisting of pyrolytic carbon. The presented results of the radiation resistance of TRISO fuel testify to the high resistance of the near-surface layer to high-dose irradiation.
这项工作的目的是对为第四代高温气冷堆（HTGR型）设计的新一代三结构各向同性颗粒燃料（TRISO）模型原型的形态、结构和强度特性进行表征。选择由内热解碳（I-PyC）、碳化硅（SiC）和外热解碳（O-PyC）组成的模型结构作为研究对象，是因为它们有可能用于制造新一代高温核反应堆燃料。为了全面评估它们的全部功能价值，有必要了解其抵抗外部影响的机制，包括机械影响，因为在运行过程中可能存在与变形相关的外部因素，并导致燃料结构表面的破坏，这将严重影响使用寿命。这些研究的目的是获得关于燃料特性及其抵抗机械摩擦产生的外部影响的新数据。此类研究对于在尽可能接近反应堆实际条件下对这种燃料进行进一步的耐腐蚀和耐辐照测试是必要的。研究表明，由于由热解碳组成的上层强度高，研究样品对外部机械影响具有高度抗性。所呈现的TRISO燃料抗辐射性结果证明了近表层对高剂量辐照具有高抗性。
