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Positron Spectroscopy of Defects in Hydrogen-Saturated Zirconium

机译:氢饱和锆中缺陷的正电子光谱

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Zirconium alloys, such as Zr-1Nb are widely used as cladding materials for nuclear fuel elements of light water reactors. Hydrogen embrittlement problem causes degradation of these parts of nuclear reactors. It is known, that hydrogen uptake causes changes in microstructure and defect structure of metals. The aim of this work is study of Zr-1Nb alloys' defect structure after hydrogen saturation up to the concentration of 600 ppm. Saturation of hydrogen was carried out from the gas phase under high temperature and pressure. This study reveals the increase of average positron lifetime with the increase of hydrogen concentration. Value of the average positron lifetime achieves plateau when the concentration of hydrogen is about 600 ppm. Also the following effects were detected in the material after hydrogen uptake up to different concentrations: crystal lattice expansion, dislocations and vacancy-like defects formation, as well as the defect-hydrogen complexes formation.
机译:锆合金,例如Zr-1NB被广泛用作轻水反应器的核燃料元件的包层材料。 氢脆问题导致这些核反应堆的降解。 众所周知,氢气吸收导致金属的微观结构和缺陷结构的变化。 这项工作的目的是在氢饱和度达到600ppm浓度后的ZR-1NB合金的缺陷结构的研究。 在高温和压力下从气相中进行氢气。 该研究揭示了随着氢浓度的增加而增加的平均正电子寿命。 当氢浓度约为600ppm时,平均正电子寿命的值实现了高原。 此外,在氢气吸收至不同浓度后,在材料中检测以下效果:晶格伸展,脱位和空位状缺陷形成,以及缺陷氢气复合物形成。

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