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Technical Brief

A Study on Hydrogen Emission of Zirconium Hydride

[+] Author and Article Information
Fu Xiaogang

China Institute of Atomic Energy,
Xinzhen, Fanshan District,
Beijing 102413, China
e-mail: fuxiaogang@ciae.ac.cn

Qin Bo

China Institute of Atomic Energy,
Xinzhen, Fanshan District,
Beijing 102413, China
e-mail: qinbo_1117@hotmail.com

Ma Haoran

China Institute of Atomic Energy,
Xinzhen, Fanshan District,
Beijing 102413, China
e-mail: mhr147741@163.com

Zhang Jinquan

China Institute of Atomic Energy,
Xinzhen, Fanshan District,
Beijing 102413, China
e-mail: zhangjin_ke@tom.com

Long Bin

China Institute of Atomic Energy,
Xinzhen, Fanshan District,
Beijing 102413, China
e-mail: binlong@ciae.ac.cn

1Corresponding author.

Manuscript received October 30, 2017; final manuscript received August 21, 2018; published online January 24, 2019. Assoc. Editor: Wenyue Zheng.

ASME J of Nuclear Rad Sci 5(1), 014501 (Jan 24, 2019) (3 pages) Paper No: NERS-17-1245; doi: 10.1115/1.4041274 History: Received October 30, 2017; Revised August 21, 2018

The hydrogen emission of zirconium hydride at high temperature is a challenging issue for many researchers. The hydrogen emission content of zirconium hydride pins should be evaluated to confirm the application feasibility. The comparison of theory analysis and experiment data indicated that Richardson's law could offer a conservative result for calculating the hydrogen emission content of zirconium hydride pins at high temperature. Furthermore, the methods of preventing hydrogen loss should be developed for the purpose of extending the work temperature or time. The results showed that a ZrO2 layer prepared for zirconium hydride could not prevent hydrogen loss after exposure at 650 °C in an inert environment and ZrO2 transformed into Zr3O gradually due to the opposite movement of hydrogen and oxygen. Finally, a further improvement to prevent hydrogen loss was developed. The zirconium hydride with a ZrO2 layer in the cladding of He+CO2 exhibited no significant reduction of hydrogen content. It is helpful to prevent the hydrogen loss by increasing the oxygen potential on the outside of ZrO2 layer.

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References

Mueller, W. M. , Blackledge, J. P. , and Libowitz, G. G. , 1968, “Hydrides in Nuclear Reactor Applications,” Metal Hydrides, Academic Press, New York, pp. 21–50.
Tsuchiya, B. , Huang, J. , Konashi, K. , Teshigawara, M. , and Yamawaki, M. , 2001, “Thermophysical Properties of Zirconium Hydride and Uranium-Zirconium Hydride,” J. Nucl. Mater., 289(3), pp. 329–333. [CrossRef]
Terrani, K. A. , Balooch, M. , Wongsawaeng, D. , Jaiyen, S. , and Olander, D. R. , 2010, “The Kinetics of Hydrogen Desorption From and Adsorption on Zirconium Hydride,” J. Nucl. Mater., 397(1–3), pp. 61–68. [CrossRef]
Ponomarev-Stepnoi, N. N. , Bubelev, V. G. , Glushkov, E. S. , Garin, V. P. , Kukharkin, N. E. , Kompaniets, G. V. , Nosov, V. I. , and Chunyaev, E. I. , 2007, “Estimation of the Hydrogen Emission From a Hydride Moderator by Measuring the Reactivity and Using Mathematical Statistics,” At. Energy, 102(2), pp. 87–93. [CrossRef]
Olander, D. , Greenspan, E. , Garkisch, H. D. , and Petrovic, B. , 2009, “Uranium–Zirconium Hydride Fuel Properties,” Nucl. Eng. Des., 239(8), pp. 1406–1424. [CrossRef]
Simnad, M. T. , 1980, “The U-ZrHx Alloy: Its Properties and Use in TRIGA Fuel,” Nucl. Eng. Des., 64(3), pp. 403–422. [CrossRef]
Forcey, K. S. , Ross, D. K. , and Simpson, J. C. B. , 1988, “Hydrogen Transport and Solubility in 316 L and 1.4914 Steels for Fusion Reactor Applications,” J. Nucl. Mater., 160(2–3), pp. 117–124. [CrossRef]
Michael, V. G. , Akira, T. , Sergey, N. R. , and Piyush, S. , 2014, “Oxidation and Hydrogen Uptake in Zirconium, Zircaloy-2 and Zircaloy-4: Computational Thermodynamics and Ab Initio Calculations,” J. Nucl. Mater., 444(1–3), pp. 65–75.

Figures

Grahic Jump Location
Fig. 3

X-ray diffraction pattern of ZrH1.85 or ZrH1.85 with a ZrO2 layer after tested in He or He+CO2 at 650 °C for 120 h

Grahic Jump Location
Fig. 2

X-ray diffraction pattern of ZrH1.8 with a ZrO2 layer after tested at 650 °C for 240 h

Grahic Jump Location
Fig. 1

Cross section of ZrH1.8 with a ZrO2 layer after tested at 650 °C for 240 h

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