Huilong Yang , Yang Liu , Mingxu Gao , Dongyue Chen , Sho Kano , Kenta Murakami , Zhengcao Li , Hiroaki Abe
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引用次数: 0
Abstract
In-situ TEM observation under heavy ion irradiation was conducted with H-free and H-charged Zr-based alloy, to reveal the synergistic effects of irradiation and hydrogenation in nuclear fuel cladding materials. Experimental results showed two aspects regarding the interaction of irradiation defects and solute H atoms in Zr-based alloy. On the one hand, the density of irradiation defects in H-charged specimen is greater relative to H-free specimen. The nucleation of irradiation loops promoted by the solute H atoms is probably due to the formation of energetically stable vacancy- hydrogen complex. On the other hand, irradiation defects play an important role in the hydride re-precipitation during cooling. Re-precipitation of hydride was observed in the H-charged specimen without irradiation, which is however absent in the irradiated specimen. This is because acting as the new sites for H atoms, irradiation defects increase solid solubility of H in Zr and therefore suppress of hydride re-precipitation upon cooling.
期刊介绍:
Scripta Materialia is a LETTERS journal of Acta Materialia, providing a forum for the rapid publication of short communications on the relationship between the structure and the properties of inorganic materials. The emphasis is on originality rather than incremental research. Short reports on the development of materials with novel or substantially improved properties are also welcomed. Emphasis is on either the functional or mechanical behavior of metals, ceramics and semiconductors at all length scales.