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首页> 外文期刊>Journal of Physics, D. Applied Physics: A Europhysics Journal >Diffusion of fission products and radiation damage in SiC
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Diffusion of fission products and radiation damage in SiC

机译:SiC中裂变产物的扩散和辐射损伤

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A major problem with most of the present nuclear reactors is their safety in terms of the release of radioactivity into the environment during accidents. In some of the future nuclear reactor designs, i.e. Generation IV reactors, the fuel is in the form of coated spherical particles, i.e. TRISO (acronym for triple coated isotropic) particles. The main function of these coating layers is to act as diffusion barriers for radioactive fission products, thereby keeping these fission products within the fuel particles, even under accident conditions. The most important coating layer is composed of polycrystalline 3C-SiC. This paper reviews the diffusion of the important fission products (silver, caesium, iodine and strontium) in SiC. Because radiation damage can induce and enhance diffusion, the paper also briefly reviews damage created by energetic neutrons and ions at elevated temperatures, i.e. the temperatures at which the modern reactors will operate, and the annealing of the damage. The interaction between SiC and some fission products (such as Pd and I) is also briefly discussed. As shown, one of the key advantages of SiC is its radiation hardness at elevated temperatures, i.e. SiC is not amorphized by neutrons or bombardment at substrate temperatures above 350 °C. Based on the diffusion coefficients of the fission products considered, the review shows that at the normal operating temperatures of these new reactors (i.e. less than 950 °C) the SiC coating layer is a good diffusion barrier for these fission products. However, at higher temperatures the design of the coated particles needs to be adapted, possibly by adding a thin layer of ZrC.
机译:当前大多数核反应堆的主要问题是在事故期间将放射性释放到环境方面的安全性。在某些未来的核反应堆设计中,即第四代反应堆,燃料为涂层球形颗粒的形式,即TRISO(三涂层各向同性的缩写)颗粒。这些涂层的主要功能是充当放射性裂变产物的扩散屏障,从而即使在事故条件下也将这些裂变产物保持在燃料颗粒内。最重要的涂层由多晶3C-SiC组成。本文综述了重要裂变产物(银,铯,碘和锶)在SiC中的扩散。由于辐射损伤会诱导和增强扩散,因此本文还简要回顾了高能中子和离子在高温(即现代反应堆运行的温度)和损伤退火过程中由高能中子和离子产生的损伤。还简要讨论了SiC与某些裂变产物(如Pd和I)之间的相互作用。如图所示,SiC的主要优点之一是其在高温下的辐射硬度,即SiC在高于350°C的温度下不会因中子或轰击而非晶化。根据所考虑的裂变产物的扩散系数,该综述表明,在这些新反应堆的正常运行温度下(即低于950°C),SiC涂层是这些裂变产物的良好扩散屏障。但是,在较高的温度下,可能需要通过添加ZrC薄层来调整涂层颗粒的设计。

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