EFFECT OF DISSOLVED OXYGEN IN STEAM ON THE CORROSION BEHAVIORS OF ZIRCONIUM ALLOYS

doi:10.11900/0412.1961.2015.00219

Acta Metall Sin

2016, Vol. 52

Issue (2): 209-216 DOI: 10.11900/0412.1961.2015.00219

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EFFECT OF DISSOLVED OXYGEN IN STEAM ON THE CORROSION BEHAVIORS OF ZIRCONIUM ALLOYS

Tianguo WEI¹,Jiankang LIN²,Chongsheng LONG¹(

),Hongsheng CHEN¹

1 Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu 610213, China
2 Fujian Fuqing Nuclear Power Co. Ltd., Fuqing 350318, China

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Tianguo WEI,Jiankang LIN,Chongsheng LONG,Hongsheng CHEN. EFFECT OF DISSOLVED OXYGEN IN STEAM ON THE CORROSION BEHAVIORS OF ZIRCONIUM ALLOYS. Acta Metall Sin, 2016, 52(2): 209-216.

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Abstract

Advanced boiling water reactors (ABWRS) show optimistic application prospect in the future. However, in these reactors, influence of dissolved oxygen (DO) on the corrosion rate of zirconium fuel claddings should be seriously considered. In this work, the effect of the dissolved oxygen (DO) on the corrosion behaviors of Zr-4, N18 (Zr-1.0Sn-0.3Nb -0.3Fe-0.1Cr) and N36 (Zr-1.0Sn-1.0Nb-0.3Fe) alloys in 400 ℃ and 10.3 MPa steam was investigated. A recirculation loop was used to control the DO level at about 0.1×10^-6 and 1.0×10^-6, respectively. The results showed that, under the two DO level conditions, N18 had almost the same weight gain as Zr-4 after exposure for 90 d, and N36 had the highest weight gain. In the initial period of the corrosion test, the three alloys had lower weight gain under higher DO level condition. With the increase of exposure time, the weight gain under 1.0×10^-6 DO level exceeded gradually the weight gain under 0.1×10^-6 level for each alloy, and the time needed for exceeding was significantly shorter for the alloy with higher Nb content.

Key words: Zr alloy corrosion behavior recirculation loop dissolved oxygen

Received: 14 April 2015

Fund: Supported by National Natural Science Foundation of China (No.51171175)

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	Tianguo WEI
	Jiankang LIN
	Chongsheng LONG
	Hongsheng CHEN

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https://www.ams.org.cn/EN/10.11900/0412.1961.2015.00219 OR https://www.ams.org.cn/EN/Y2016/V52/I2/209

Table 1 Chemical compositions of Zr alloys (mass fraction / %)

Fig.1 TEM images of N18 (a) and N36 (b) alloys

Table 2 Compositions of second phase particles in N18 and N36 alloys in Fig.1 (mass fraction / %)

Fig.2 Curves of weight gain vs exposure time for Zr-4 (a), N18 (b), and N36 (c) alloys in 400 ℃ and 10.3 MPa steam with 0.1×10^-6 and 1.0×10^-6 dissolved oxygen (DO)

Fig.3 Surface morphologies of the oxide films formed on Zr-4 (a) and N18 (b) alloys (90 d, 0.1×10^-6 DO)

Fig.4 Morphologies of a mature nodule (a) and initial nodules (b, c) on the oxide surface of Zr-4 (a, b) and N18 (c) alloys (90 d, 1.0×10^-6 DO) (Arrows show the nodule forming regions)

Fig.5 Cross-sectional morphologies of the oxide layers formed on Zr-4 (a), N18 (b), N36 (c) alloys, and the magnified image of the framed part in Fig.5c (d) (90 d, 1.0×10^-6 DO, arrows show the cracks)

Fig.6 Cracks at the surrounding of the second phase particles (SPPs) in the oxide film of Zr-4 (a) and N18 (b) alloys (60 d, 1.0×10^-6 DO)

Fig.7 Morphology of the oxide formed on metallic Nb after 2 d exposure under 0.1×10^-6 DO

Fig.8 XRD spectrum of the oxide formed on metallic Nb

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