在模拟核电一回路的高温高压水环境中，采用慢应变速率拉伸方法，研究不同应变速率下锻造316L不锈钢的应力腐蚀行为，并通过扫描电镜对试样断口形貌进行分析。结果表明，在290℃的高温高压水环境中，随着应变速率的降低，材料的应力腐蚀敏感性逐渐增强。当应变速率为2×10-5 s-1时，断口未发现脆性解理特征。应变速率为2×10-6 s-1时，在290℃和320℃两种服役温度下，材料都具有一定应力腐蚀开裂倾向，敏感性随温度的升高也略有增强。当应变速率降为1×10-6 s-1时，断口边缘呈现明显的脆性解理断裂特征。使用修正的Arrhenius模型来描述锻造316L不锈钢高温高压环境下拉伸时的本构关系，计算出变形激活能Q=213.7 kJ/mol，并得到了其高温拉伸本构方程，由本构方程计算得到的抗拉强度和试验所测值的平均相对误差为0.45%，说明该本构方程能较准确计算出锻造316L不锈钢在不同高温高压条件下的抗拉强度。
徐连勇
,
王浩
,
赵雷
,
荆洪阳
,
韩永典
. 国产锻造态316L不锈钢在高温高压水环境中的应力腐蚀行为研究[J]. 机械工程学报, 2018
, 54(10)
: 53
-58
.
DOI: 10.3901/JME.2018.10.053
In high temperature and high pressure water of a simulated primary circuit of PWR environment, the stress corrosion cracking behavior of forged 316L stainless steel under different strain is investigated by means of slow strain rate testing (SSRT). And the fracture morphology of specimens is analyzed with the aid of scanning electron microscopy.The results show that the stress corrosion cracking(SCC) susceptibility of 316L stainless steel increases with the decrease of SSRT rate in the 290℃ high temperature water. At the strain rate of 2×10-5 s-1, no obvious cleavage character is found on the fracture surfaces. At the strain rate of 2×10-6 s-1, the material shows the clear tendency of brittle fracture characteristics both at the 290℃ and 320℃,while the susceptibility increases slightly with temperature. At the strain rate of 1×10-6 s-1, the edge fracture morphology of the specimen presents brittle fracture characteristics. The modified Arrhenius model is used to describe the high temperature and high pressure tension constitutive equation of 316 stainless steel. By calculation, the activation energy Q is about 213.7 kJ/mol, then the high temperature tensile constitutive equation is obtained. The ultimate stress values predicted by proposed model has a low value of relative error(0.45%). So this constitutive equation is some accurate to get the ultimate stress of forged 316L stainless steel in high temperature and pressure water.
[1] ZENG Ming,LIU Yingxin,OUYANG Shaojie. Nuclear energy in the Post-Fukushima Era:Research on the developments of the Chinese and worldwide nuclear power industries[J]. Renewable and Sustainable Energy Reviews,2016,58:147-156.
[2] BALDO M,BURGIO G F. The nuclear symmetry energy[J]. Progress in Particle and Nuclear Physics,2016,91:203-258.
[3] YANG Wu,LI Guangfu,HUANG Chunbo. Stress corrosion cracking of nitrogen-containing stainless steel 316LN in high temperature water environments[J]. Chinese Journal of Mechanical Engineering,2010,23(6):677-683.
[4] SUN Jiao,CHEN Songying,QU Yanpeng. Review on stress corrosion and corrosion fatigue failure of centrifugal compressor impeller[J]. Chinese Journal of Mechanical Engineering,2015,28(2):217-225.
[5] SAEZ M A,GOMEZ B D. Stress corrosion cracking behavior of annealed and cold worked 316L stainless steel in supercritical water[J]. Nuclear Engineering and Design,2016,307:30-38.
[6] SCOTT P M. A review of environment sensitive fractures in water reactor materials[J]. Corrosion Science,1985,25(8):583-606.
[7] YVON P,CARRE F. Structural materials challenges for advanced reactor systems[J]. Journal of Nuclear Materials,2009,385(2):217-222.
[8] 潘品李,钟约先,马庆贤. 核电主管道锻件锻造成形均匀性模拟研究[J]. 机械工程学报,2013,49(10):97-102. PAN Pinli,ZHONG Yuexian,MA Qingxian. Simulation on forming uniformity of nuclear main pipe forging[J]. Journal of Mechanical Engineering,2013,49(10):97-102.
[9] FERON D,HERMS E. Behavior of stainless steels in pressurized water reactor primary circuits[J]. Journal of Nuclear Materials,2012,427:364-377.
[10] XIE Xingfei,NING Dong,CHEN Bin. Stress corrosion cracking behavior of cold-drawn 316 austenitic stainless steels in simulated PWR environment[J]. Corrosion Science,2016,112:576-584.
[11] 关矞心,李岩,董超芳. 高温水环境下温度对316L不锈钢应力腐蚀开裂的影响[J]. 北京科技大学学报,2009,31(9):1122-1126. GUAN Juxin,LI Yan,DONG Chaofang. Effect of temperature on stress corrosion cracking of 316L stainless steel in hightemperature water[J]. Journal of University of Science and Technology Beijing,2009,31(9):1122-1126.
[12] ZHONG Yunpan,ZHOU Cheng,CHEN Songying. Effects of temperature and pressure on stress corrosion cracking behavior of 310S stainless steel in chloride solution[J]. Chinese Journal of Mechanical Engineering,2017,30(1):200-206.
[13] 曹建国,王天聪,李洪波. 基于Arrhenius改进模型的无取向电工钢高温变形本构关系[J]. 机械工程学报,2016,52(4):90-96. CAO Jianguo,WANG Tiancong,LI Hongbo. High temperature constitutive relationship of non-oriented electrical steel based on modified arrhenius model[J]. Journal of Mechanical Engineering,2016,52(4):90-96.
[14] QU Yanpeng,WANG Runkun,WANG Chao. Experimental study on the stress corrosion cracking behavior of AISI347 in acid chloride ion solution[J]. Results in Physics,2016,6:690-697.
[15] FENG Xu,ZHOU Jianzhong,MEI Yufen. Improving tribological performance of gray cast iron by laser peening in dynamic strain aging temperature regime[J]. Chinese Journal of Mechanical Engineering,2015,28(5):904-910.
[16] DU Donghai,CHEN Kai,LU Hui. Effects of chloride and oxygen on stress corrosion cracking of cold worked 316/316L austenitic stainless steel in high temperature water[J]. Corrosion Science,2016,110:134-142.
[17] JANG M H,KANG J Y,JANG J H. Hot deformation behavior and microstructural evolution of alumina-forming austenitic heat-resistant steels during hot compression[J]. Materials Characterization,2017,123:207-217.
