采用U型弯曲试样研究了高、低温工厂退火状态的压水堆蒸汽发生器(SG)商用化600合金管在330℃、含10g/L PbO的10%NaOH高温水溶液中的应力腐蚀开裂(SCC)行为.结果表明,在氢浓度很高时,600合金表现为较严重的晶间腐蚀(IGA),最大侵蚀深度约270 μm;没有观察到明显的应力腐蚀开裂,腐蚀晶界中有铅的沉积;冷拉预变形、退火温度对材料的腐蚀和应力腐蚀行为的影响不明显.
参考文献
| [1] | Staehle R W,Gorman J A.Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing pressurized water reactors:Part 1[J].Corrosion,2003,59(11):943. |
| [2] | Scott P M.A review of environment-sensitive fracture in water reactor materials[J].Corrosion Science,1985,25 (8/9):601. |
| [3] | Staehle R W.Chemistry and electrochemistry of corrosion and stress corrosion cracking[A].Jones Russel H.A Symposium Honoring the Contributions of Staehle R W[C].New Orleans:TMS,2001.401. |
| [4] | Rooyen D V.Review of the stress corrosion cracking of Inconel 600[J].Corrosion,1975,31 (9):327. |
| [5] | Miglin B P,Sarver J M,Psaila-Dombrowksi M J,et al.Lead assisted stress corrosion cracking of nuclear steam generator tubing materials[A].Proceedings of Improving the Understanding and Control of Corrosion on the Secondary Side of Steam Generators[C].Airlie:NACE,1995.95. |
| [6] | Castano-Marin M L,Gomez-Briceno D,Hernandez-Arroyo F.Influence of lead contamination on the stress corrosion resistance of nickel alloys[A].Gold R E,Simonen E P.Proceedings of Sixth International Symposium on the Environmental Degradation of Materials in Nuclear Power Systems-water Reactors[C].New Orleans:TMS,1993.196. |
| [7] | Kim U C,Kim K M,Lee E H.Effects of chemical compounds on the stress corrosion cracking of steam generator tubing materials in a caustic solution[J].Journal of Nuclear Materials,2005,(341):174. |
| [8] | Pement F W,Wilson I L W,Aspden R G.Stress corrosion cracking studies of high nickel austenitic alloys in several high temperature aqueous solutions[J].Materials Performance,1980,19(4):48. |
| [9] | 卢建树,王保峰,张九渊.高温水中不锈钢和镍基合金应力腐蚀破裂研究进展[J].核动力工程,2001,22(3):259. |
| [10] | 华惠中,黄春波,吕战鹏,等.800、600和690合金的铅致应力腐蚀破裂[J].腐蚀与防护,2001,22(11):483. |
| [11] | 沈长斌,陶晓杰,杨怀玉,等.高温高压水环境下传热管失效形式及防腐措施研究进展[J].腐蚀科学与防护技术,2003,15(4):223. |
| [12] | Sui G,Titchmarch J M,Heys G B,et al.Stress corrosion cracking of alloy 600 and alloy 690 in hydrogen/steam at 380℃[J].Corrosion Science,1997,39 (3):583. |
| [13] | Thomas L E,Bruemmer S M.High-resolution characterizatian of intergranular attack and stress corrosion cracking of alloy 600 in high-temperature primary water[J].Corrosion,2000,56(6):573. |
| [14] | Yi Y,Kim H,Park Y,et al.Effect of an inhibitor on the stress corrosion cracking behavior of alloy 600 in a high-temperature caustic solution[J].Corrosion,2005,61 (5):405. |
| [15] | [苏]M古特曼,著,金石,译.金属力学化学与腐蚀防护[M],北京:科学出版社,1989.66. |
| [16] | Sakai T,Nakagomi N,Kikuchi T,et al.Mechanism of lead-induced stress corrosion cracking of nickel-based alloys in hightemperature water[J].Corrosion,1998,54 (7):522. |
| [17] | Hwang S S,Kim J S.Electrochemical interaction of lead with alloy 600 and alloy 690 in high-temperature water[J].Corrosion,2002,58 (5):397. |
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