国产新型锆合金SZA-4、SZA-6管材氢化物应力再取向研究
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摘要
采用氢氩气相渗氢法、慢速率拉伸实验机进行氢化物应力取向及再取向实验,利用金相显微镜和Mias图像处理系统等方法,研究了环向应力和热循环次数对SZA-4和SZA-6两种国产新型锆合金管材氢化物应力再取向的影响。结果表明,SZA-4管材和SZA-6管材的应力取向因子(F_N(40°))随着应力和热循环次数的增加而增大,然后逐渐趋于N稳定,且SZA-6管材比SZA-4管材更易发生氢化物应力再取向0。对于SZA-4管材,F_N(40°)不大于0.45;SZA-6管材,F_N(40°)不大于0.7。
The effects of loop stress and thermal cycling times on the hydride stress reorientation behavior of two kinds of domestic zircalloy SZA-4 and zircalloy SZA-6 tubing were studied by carrying out hydride stress orientation and reorientation test with hydrogen argon gas permeability method and slow rate tensile testing machine and using metallographic microscope and Mias image processing system. The results show that the stress orientation factor( F_N(40°)) of SZA-4 and SZA-6 tubing Nincreases with the increase of the stress and the numbers of thermal cycling times, and then tends to become stable. The hydride stress reorientation is easier to occur in SZA-6 tubing than that in SZA-4 tubing. For SZA-4 tubing, the obtained F_N(40°) is less than 0.45, and for SZA-6 tubing, the obtained F_N(40°) is less than 0.7.
The effects of loop stress and thermal cycling times on the hydride stress reorientation behavior of two kinds of domestic zircalloy SZA-4 and zircalloy SZA-6 tubing were studied by carrying out hydride stress orientation and reorientation test with hydrogen argon gas permeability method and slow rate tensile testing machine and using metallographic microscope and Mias image processing system. The results show that the stress orientation factor( F_N(40°)) of SZA-4 and SZA-6 tubing Nincreases with the increase of the stress and the numbers of thermal cycling times, and then tends to become stable. The hydride stress reorientation is easier to occur in SZA-6 tubing than that in SZA-4 tubing. For SZA-4 tubing, the obtained F_N(40°) is less than 0.45, and for SZA-6 tubing, the obtained F_N(40°) is less than 0.7.
引文
[1] Stéphane Valance, Johannes Bertsch.Hydrides reorientationinvestigation of high burn-up PWR fuel cladding[J]. Journal ofNuclear Materials,2015:371-381.
[2] Kim Juseong, Kim Youngjun, Kook Dong H, et al.A studyon hydride reorientation of Zircaloy-4 cladding tube under stress[J].Journal of Nuclear Materials, 2015,456:246-252.
[3] Cha HyunJin, Won JuJin, Jang KiNam, et al.Tensile hoopstres s-,hydrogen content-and cooling rate-dependent hydridereorientation behaviors of Zr alloy cladding tubes[J]. Journalof Nuclear Materials,2015,464:53-60.
[4] Jin Cha Hyun, Jang KiNam, An JiHyeong, et al.The effect ofhydrogen and oxygen contents on hydride reorientations ofzirconium alloy cladding tubes[J].Nuclear Engineering andTechnology,2015,47:746-755.
[5]彭倩,沈保罗.锆合金的织构及其对性能的影响[J].稀有金属,2005,29(6):903-908.
[2] Kim Juseong, Kim Youngjun, Kook Dong H, et al.A studyon hydride reorientation of Zircaloy-4 cladding tube under stress[J].Journal of Nuclear Materials, 2015,456:246-252.
[3] Cha HyunJin, Won JuJin, Jang KiNam, et al.Tensile hoopstres s-,hydrogen content-and cooling rate-dependent hydridereorientation behaviors of Zr alloy cladding tubes[J]. Journalof Nuclear Materials,2015,464:53-60.
[4] Jin Cha Hyun, Jang KiNam, An JiHyeong, et al.The effect ofhydrogen and oxygen contents on hydride reorientations ofzirconium alloy cladding tubes[J].Nuclear Engineering andTechnology,2015,47:746-755.
[5]彭倩,沈保罗.锆合金的织构及其对性能的影响[J].稀有金属,2005,29(6):903-908.