Zr-2.5Nb压力管材的氧化腐蚀行为影响因素
Influence Factors of Corrosion Behavior of Zr-2. 5Nb Pressure Tube
摘 要
从Zr-2. 5Nb压力管上切下3种具有不同取向的试样,在10 MPa和1 MPa的400 ℃高温蒸汽中进行氧化试验。采用各种微观观察技术对试样的形貌、成分和织构进行研究。结果表明:降低预膜处理工艺中的蒸汽压力并不会造成预生氧化膜的减薄,可以对预膜处理工艺中的蒸汽压力进行优化以取得更好的经济效益。取向对材料的腐蚀氧化有显著影响,端面(R-T面)较其余面的氧化速度更快。氧化后试样侧面(L-R面)出现条带状凹坑,这是β-Nb氧化脱落所致。低晶界密度、更紧凑的原子排列以及沿管子轴向拉长富Nb带都是造成管材侧面(L-R面)和曲面(L-T)具有更好耐蚀性的原因。
晶粒取向
织构
腐蚀行为
Zr-2. 5Nb
grain orientation
texture
corrosion behavior
Abstract
Three samples with different orientations were cut from Zr-2. 5Nb pressure pipe and subjected to oxidation tests in 400 ℃ high-temperature steam at 10 MPa and 1 MPa. The morphology, composition, and texture of the samples were studied using several micro observation techniques. The results indicated that reducing the steam pressure in the pre film treatment process did not cause thinning of the pre formed oxide film, and could optimize the steam pressure in the pre film treatment process to achieve better economic benefits. Orientation had a significant impact on the corrosion and oxidation of the samples, with the oxidation rate of the end face (R-T face) being faster than that of the other surfaces. After oxidation, strip shaped pits appeared on the side (L-R surface) of the sample, which was β- Caused by Nb oxidation and detachment. Low grain boundary density, more compact atomic arrangement, and elongation of Nb rich bands along the axial direction of the pipe were all reasons for high corrosion resistance on the side (L-R surface) and curved surface (L-T) of the pipe.
中图分类号 TG172 DOI 10.11973/fsyfh-202310005
所属栏目 试验研究
基金项目
收稿日期 2022/1/20
修改稿日期
网络出版日期
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引用该论文: WANG Yatong,LAI Ping,ZHANG Miaomiao,LYU Kang,ZHAO Guannan,ZHANG Lefu,GUO Xianglong. Influence Factors of Corrosion Behavior of Zr-2. 5Nb Pressure Tube[J]. Corrosion & Protection, 2023, 44(10): 25
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【3】DUAN Z, YANG H, SATOH Y, et al. Current status of materials development of nuclear fuel cladding tubes for light water reactors[J]. Nuclear Engineering and Design, 2017,316:131-150.
【4】MOTTA A T,COUET A,COMSTOCK R J.Corrosion of zirconium alloys used for nuclear fuel cladding[J].Annual Review of Materials Research,2015,45:311-343.
【5】RALSTON K D,BIRBILIS N.Effect of grain size on corrosion:a review[J].Corrosion,2010,66(7):75005.
【6】ZHANG X Y, SHI M H, LI C, et al. The influence of grain size on the corrosion resistance of nanocrystalline zirconium metal[J]. Materials Science and Engineering:A, 2007,448:259-263.
【7】YONG H J, KIM H G, KIM T H. Effect of β phase, precipitate and Nb-concentration in matrix on corrosion and oxide characteristics of Zr-xNb alloys[J]. Journal of Nuclear Materials, 2003,317:1-12.
【8】YAO M Y, GAO C Y, HUANG J, et al. Oxidation behavior of β-Nb precipitates in Zr-1Nb-0.2Bi alloy corroded in lithiated water at 360℃[J]. Corrosion Science, 2015,100:169-176.
【9】JEONG Y H,PARK S Y,LEE M H,et al.Out-of-pile and In-pile perfomance of advanded zirconium alloys (HANA) for high burn-up fuel[J].Journal of Nuclear Science and Technology,2006,43(9):977-983.
【10】ZHOU B X,YAO M Y,LI Z K,et al.Optimization of N18 zirconium alloy for fuel cladding of water reactors[J].Journal of Materials Science & Technology,2012,28(7):606-613.
【11】PROFF C,ABOLHASSANI S,LEMAIGNAN C.Oxidation behaviour of zirconium alloys and their precipitates-A mechanistic study[J].Journal of Nuclear Materials,2013,432(1/2/3):222-238.
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【14】TENCKHOFF E.Review of deformation mechanisms,texture,and mechanical anisotropy in zirconium and zirconium base alloys[M]//Zirconium in the Nuclear Industry:Fourteenth International Symposium.West Conshohocken:ASTM International,2008:25-25-26.
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【21】BRADLEY E R, SABOL G P. Zirconium in the nuclear industry[C]//Eleventh international symposium, ASTM International.[S.l.]:[s.n.], 1994.
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【24】PROFF C,ABOLHASSANI S,LEMAIGNAN C.Oxidation behaviour of binary zirconium alloys containing intermetallic precipitates[J].Journal of Nuclear Materials,2011,416(1/2):125-134.
【25】LAI P,LU J Q,ZHANG H,et al.The corrosion behavior of M5(Zr-1Nb-0. 12O) alloy in 360℃ water with dissolved oxygen[J].Journal of Nuclear Materials,2020,532:152079.
【26】YILMAZBAYHAN A, MOTTA A T, COMSTOCK R J, et al. Structure of zirconium alloy oxides formed in pure water studied with synchrotron radiation and optical microscopy:relation to corrosion rate[J]. Journal of Nuclear Materials, 2004,324:6-22.
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【31】YILMAZBAYHAN A, BREVAL E, MOTTA A T, et al. Transmission electron microscopy examination of oxide layers formed on Zr alloys[J]. Journal of Nuclear Materials, 2006,349:265-281.
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