。1126 北京科技大学学报 第31卷 断裂(EAC).应变速率很低时DSA多发生在100~ ronments.Corrasion,1993,49(1):8 350℃的温度范围内，并且由于晶间夹杂物质如N [4 Congleton J.Berrisford R A.Yang Wu.Stress corrosion cracking 和C的扩散而更明显.虽然DSA不是发生环境敏 of sensitized type 304 stainless steel in dped high-temperature waer.Cor mosi0m,199551(12):901 感断裂的前提条件，但Couvant1g等认为有明显的 【习Asakum Y,Karasawa H。etal.Relationships bet ween cormosion 证据显示，DSA和EAC敏感性与温度的关系是一 behavior of AlSI 304 stainless steel in high temperature pure wa 致的：EAC与温度关系表现为裂纹扩展速率在某一 ter and its oxide film structu res.Corrosion,1989,45(2):119 温度下出现一峰值：而DSA与温度的关系表现在断 [6 Andresen P L.Effects of temperature on crack growth rate in sensitized type 304 stainless steel and Alloy 600.Corrosion, 面收缩率在同一温度下出现一谷值.这个极值点所 199349(9):714 对应的温度就是发生SCC的敏感温度，本实验中的 [n Zhang D K.Localized Corrosion of Stainless Stel.Beijing:Sci- 敏感温度即250℃.DSA是通过促进平面变形而增 ence Press 1982:291 强局部塑性变形，从而促进脆性裂纹扩展同时它还 (张德康.不锈钢局部腐蚀.北京：科学出版社，1982：291) 可能影响氧化膜破裂，增加裂纹扩展速率，这些还需 [8 Li H M.Cai X LvZ P.et al.Analysis of su dface oxide films on 做进一步研究. stwess cormosion cracking pecimens of type 304 stainless steel in high temperature water containing boric acid and lithium ion. 3结论 Mater Eng2004(4):7 (李红梅，蔡询吕战鹏等.304不锈钢在含硼和锂的高温水 (1)在200~345℃高温水环境中，316L不锈 中的应力腐蚀破裂和表层氧化膜分析.材料工程，2004(4)： 7) 钢的失效模式为脆性断裂和韧性断裂同时存在，以 [9 Gao X Wu X Q.Guan H.et al.Progress in study cormosion 韧性断裂为主，说明316L不锈钢在此环境下的应 scale formedin hightemperature and highpressure water.Corros 力腐蚀开裂敏感性较低. Sci Prat Technol,2007(2):110 (2)在250℃高温水环境中，316L不锈钢试样 (高欣，吴欣强关辉，等.高温高压水环境下腐蚀产物膜的研 的最大抗拉强度、总延伸率、断面收缩率和断裂时间 究现状.腐蚀科学与防护技术，2007(2)：110) 的下降均表明材料的脆性增加，250℃是316L不锈 [10 Zuo J Y.Stress Corrosion Crack.Xi'an:Xi'an Jiaotong Uri- versity Press 1985:218 钢在此环境中易发生应力腐蚀开裂的敏感温度，应 (左景伊.应力腐蚀破裂.西安：西安交通大学出版社，1985： 避免材料在此温度附近服役. 218) (3)在200~345℃高温水环境中，温度与316L 11]Chopma O K,Soppet W K.Shack W J.Effects of Alloy Cem- 不锈钢$CC敏感性之间的关系并非单调递增或递 istry,Cold Work.and Water Chemistry on Cor osion Fatigue 减温度通过腐蚀电位、裂纹开裂速率和氧化膜破裂 and Stress Cor rosion Cracking of Nickel Albys and Welds.Ar gonne Argonre National Laboratory,2001:35 等过程来影响应力腐蚀开裂过程，而影响机理有待 [12]Andresen P L Ford F P.Gott K.Expert Panel Report on 于进一步研究. Proactive Materials Degradation Assessment.New York: Bmookhaven National Laboratory,2006:B-I 参考文献 13 Jones R H.Henager C H Jr.Effect of gamma irradiation on [1]Ruther W E Soppet W K,Kassner T F.Effect of temperature stress corsion behavior of austenitic stainless steel under ITER and ioric impurities at very low concent rations on stress corrosion relevant conditions.J Nuc/Mater,1992.19F194:1012 cracking of A II 304 stainless stedl.Corrasion.1988.44(11): [14 Katada Y.Nagata N.The effect of temperature on fatigue crack 791 growth behavior of a bw-alloy pressure vessel steel in a simuated [2]Yang W.Zhao G Z.Zhang M J et al.An AES investigation of BWR environment.Corrosion Sci,1985,25:693 the surface films fomed stress corrosion test specimens of type 15]Atkinson J D.Yu J.Role of dynamic strain-ageing in the envi- 304 stainless steel in high temperat ure.Corros Sci,1992.33 ronment assisted cracking observed in pressure vessel steels.Fa- (1):89 tigue Fract Eng Mater Struct.1997.20:1 [3]MacDonald DD.Song H.Yoshida K.Corrosion potential mea 16 Couvant T,Massoud J.Envin menta lly Assisted Cracking. surements on type 304SS and alloy 182 in simulated BW R envi Moret sur Loing France,2006:3断裂(EAC).应变速率很低时 DSA 多发生在 100 ～ 350 ℃的温度范围内 , 并且由于晶间夹杂物质如 N 和C 的扩散而更明显 .虽然 DSA 不是发生环境敏 感断裂的前提条件, 但 Couvant [ 16] 等认为有明显的 证据显示, DSA 和 EAC 敏感性与温度的关系是一 致的:EAC 与温度关系表现为裂纹扩展速率在某一 温度下出现一峰值;而 DSA 与温度的关系表现在断 面收缩率在同一温度下出现一谷值.这个极值点所 对应的温度就是发生 SCC 的敏感温度, 本实验中的 敏感温度即 250 ℃.DSA 是通过促进平面变形而增 强局部塑性变形 ,从而促进脆性裂纹扩展,同时它还 可能影响氧化膜破裂 ,增加裂纹扩展速率,这些还需 做进一步研究. 3 结论 (1)在 200 ～ 345 ℃高温水环境中 , 316 L 不锈 钢的失效模式为脆性断裂和韧性断裂同时存在 , 以 韧性断裂为主, 说明 316 L 不锈钢在此环境下的应 力腐蚀开裂敏感性较低. (2)在 250 ℃高温水环境中, 316 L 不锈钢试样 的最大抗拉强度 、总延伸率、断面收缩率和断裂时间 的下降均表明材料的脆性增加 , 250 ℃是 316 L 不锈 钢在此环境中易发生应力腐蚀开裂的敏感温度 , 应 避免材料在此温度附近服役. (3)在 200 ～ 345 ℃高温水环境中, 温度与316 L 不锈钢 SCC 敏感性之间的关系并非单调递增或递 减,温度通过腐蚀电位、裂纹开裂速率和氧化膜破裂 等过程来影响应力腐蚀开裂过程 ,而影响机理有待 于进一步研究. 参 考 文 献 [ 1] Ruther W E , S oppet W K , Kassner T F .Eff ect of t emperature and ioni c impurities at very low concentrations on stress corrosion cracking of AIS I 304 st ainless steel.Corrosion , 1988 , 44(11): 791 [ 2] Yang W, Zhao G Z , Zhang M J, et al.An AES investigation of the surface films formed stress corrosion test specimens of type 304 st ainless steel in high t emperature.Corros Sci , 1992 , 33 (1):89 [ 3] MacDonald D D , Song H , Yoshida K.Corrosion poten tial mea￾surements on type 304S S and alloy 182 in simulated BWR envi￾ronments.Corrosion , 1993 , 49(1):8 [ 4] Congleton J, Berrisf ord R A , Yang Wu.S tress corrosion cracking of sensitized type 304 st ainless steel in doped high-temperatu re w ater .Corrosion , 1995 , 51(12):901 [ 5] Asakura Y, Karasawa H , et al.Relationships between corrosion behavior of AIS I 304 stainless st eel in high temperature pu re w a￾ter and its oxide film structu res.Corrosion , 1989 , 45(2):119 [ 6] Andresen P L .Effects of temperature on crack grow th rate in sensitized type 304 st ainless st eel and Alloy 600.Corrosion , 1993 , 49(9):714 [ 7] Zhang D K .Localiz ed Corrosion of S tainless S teel .Beijing :Sci￾ence Press, 1982:291 (张德康.不锈钢局部腐蚀.北京:科学出版社, 1982:291) [ 8] Li H M , Cai X, Lv Z P , et al.Analysis of su rf ace oxide films on stress corrosion cracking specimens of type 304 stainless st eel in high t emperature w ater con taining bori c acid and lithium ion.J Mater E ng , 2004(4):7 (李红梅, 蔡 , 吕战鹏, 等.304 不锈钢在含硼和锂的高温水 中的应力腐蚀破裂和表层氧化膜分析.材料工程, 2004(4): 7) [ 9] Gao X, Wu X Q , Guan H , et al.Progress in study corrosion scale f ormed in high-t emperature and high-p ressure water .Corros S ci Prot Tech nol , 2007(2):110 (高欣, 吴欣强, 关辉, 等.高温高压水环境下腐蚀产物膜的研 究现状.腐蚀科学与防护技术, 2007(2):110) [ 10] Zuo J Y .S tress Corrosion Crack .Xi' an:Xi' an Jiaot ong Uni￾versity Press, 1985:218 (左景伊.应力腐蚀破裂.西安:西安交通大学出版社, 1985: 218) [ 11] Chop ra O K , S oppet W K, Shack W J.E ff ects of Alloy Chem￾istry , Cold Work , an d Water Chemistry on Corrosion Fatigue and S tress Corrosion Cracking of Nickel Alloys a nd Welds .Ar￾gonne:Argonne National Laboratory , 2001:35 [ 12] Andresen P L , Ford F P, Gott K .E xpert Panel Report on Proactive Materials Degradation Assessment . New York: Brookhaven National Laboratory , 2006:B-1 [ 13] Jones R H , Henager C H Jr .Eff ect of gamma irradiation on stress corrosion behavior of austenitic st ainless steel under IT ER￾relevant conditions.J Nucl Mat er , 1992 , 191-194:1012 [ 14] Katada Y , Nagat a N .T he effect of t emperature on f atigue crack grow th behavior of a low-alloy pressure vessel steel in a simulated BWR environment.Corrosion S ci , 1985 , 25:693 [ 15] Atkinson J D, Yu J.Role of dynamic strain-ageing in the envi￾ronmen t assisted cracking observed in pressu re vessel st eels.Fa￾tigue Fr act Eng Ma ter Struct , 1997 , 20:1 [ 16] Couvant T , Massoud J.E nvin menta lly Assisted Cracking . Moret sur Loing France , 2006:3 · 1126 · 北 京 科 技 大 学 学 报 第 31 卷