锆合金中的氢化物脱附行为研究进展

doi:10.11896/cldb.18100184

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Abstract Zirconium alloys have been widely used in nuclear reactors due to their strong corrosion resistance and low thermal neutron absorption interface. After more than 60 years’ development, zirconium alloys have evolved from the first generation of zirconium-1 alloys to the second generation of zirconium-2, zirconium-4 alloys and the third generation of N36, ZIRLO, M05 alloys. Hydrogen precipitation will reduce the mecha-nical properties of zirconium alloys. Hydrogen mainly comes from the corrosion reaction between zirconium and water, which enters the metal matrix through diffusion and retains in the matrix. The types and properties of hydrides in zirconium alloys have attracted much attention. So far, there are four types of hydrides, but two of them (ζ-ZrH_0.5(bct) and γ-ZrH (fct)) are metastable. Moreover, the presence of ζ phase hydride is extremely short, the current experimental equipment or experimental methods cannot be observed at such a short time scale. Hence, many experimental studies on hydrides are concentrated in δ-ZrH_1.4-1.7 (fcc) and ε-ZrH₂(fct).
　　The working environment of the zirconium alloys is high temperature, while the retained hydrogen in the matrix will desorb at high temperature and lead to the distortion caused by precipitate phase disappear. During this cycle, many micro defects gradually accumulate inside the material, then accelerate the materials aging. It was found that many researchers used pure ZrH₂ powder to study the desorption behavior of hydrogen in zirconium, but the actual serviced zirconium alloys contain other alloying elements, their existence will affect the retention state and desorption behaviors of hydrogen. Thermal desorption spectroscopy (TDS) is one of the effective ways to investigate the retention state of hydrogen and its isotopes in metals and alloys, however, TDS has certain limitations in determining the desorption behavior of hydrogen in zirconium alloy. Besides, the surface of zirconium alloys commonly covered by an oxide layer. When hydrogen diffuses into the oxide layer, the oxygen atoms in the oxide layer will trap some hydrogen atoms by forming hydrogen-oxygen bond. This bond reduces the amount of desorption, delays the desorption, and rises the desorption temperature. Therefore, the increase in desorption temperature on the experimental data does not mean that the actual desorption temperature of the hydride in the matrix, but the process of hydrogen diffusion is blocked by the oxide layer.
　　This review summarizes the research progress of the desorption behavior of zirconium hydride, introduces the structure of hydrides, the source of hydrogen, the hydrogen retention state, the limitations of TDS and the desorption behavior of hydrides respectively, points out the shortco-mings of the research in desorption behavior of zirconium hydrides and prospects the future research directions.

Key words： reactor cladding zirconium alloy hydrides thermal desorption spectroscopy (TDS) method zirconium dioxide

Published: 16 January 2020

CLC number:

TL341

About author:: Zhenfei Yangreceived his B.E. degree in metal materials and engineering from Sichuan University in 2016. He is currently pursuing his master’s degree at the Institute of Materials, China Academy of Engineering Physics under the supervision of researcher Bingyun Ao. His research focused on the influence of alloying elements on the desorption behaviors of zirconium hydrides;Bingyun Ao, Ph.D., researcher. He is mainly engaged in the experimental and theoretical research of nuclear materials, and is responsible for a number of scientific research projects including the Science Challenge Program, the National Natural Science Foundation, and the National Defense System Advance Research Project. He has published more than 50 acade-mic papers in the field of nuclear materials and has been invited to participate in domestic and international academic conferences in the field of nuclear materials for many times, and make special invitation reports or invitation reports. He has won the 13th Deng Jiaxian Youth Science and Technology Award for the innovation achievements in nuclear material aging experiments and theoretical research.

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Cite this article:

YANG Zhenfei,SHI Peng,AO Bingyun. Research Progress on the Desorption Behavior of Hydrides in Zirconium Alloys[J]. Materials Reports, 2020, 34(5): 5102-5108.

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http://www.mater-rep.com/EN/10.11896/cldb.18100184 OR http://www.mater-rep.com/EN/Y2020/V34/I5/5102

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