将Zr-Sn-Nb-Fe锆合金样品分别进行不同热处理,在350℃、16.8 MPa、0.01 mol·L-1 LiOH高压水溶液中腐蚀,并用高分辨透射电镜(HR-TEM)研究它们的显微组织和析出相粒子.结果表明,冷轧前在800℃保温的两种样品的耐腐蚀性能好于680℃保温的两种样品,冷轧后500℃保温样品的耐腐蚀性能好于560℃保温样品.HR-TEM分析表明800℃/500℃处理样品耐腐蚀性能最好的原因是析出相粒子中Nb含量较高,从而降低了Nb元素在基体αZr中的固溶含量.
参考文献
[1] | Thorvaldsson T;Andersson T;Wilson A.Correlation between 400℃ steam corrosion behavior,heat treatment,and microstructure of Zircaloy-4 tubing[A].Philadelphia,1989:128-140. |
[2] | Foster J P;Dougherty J;Burke M G et al.Influence of final recrystallization heat treatment on Zircaloy-4 strip corrosion[J].JOURNAL OF NUCLEAR MATERIALS,1990,173:164-178. |
[3] | ZHOU Bang-xin;ZHAO Wen-jin;MIAO Zhi et al.The effect of heat treatment on the corrosion behavior of Zircaloy-4[R].China Nuclear Science and Technology Report,CNIC-01074,SINRE-0066,China Nuclear Information Center,Atomic Energy Press,1996. |
[4] | Back J H;Jeong Y H;Kim I S .Effect of the accumulated annealing parameter on the corrosion characteristics of a Zr-0.5Nb-1.0Sn-0.5Fe-0.25Cr alloy[J].Journal of Nuclear Materials,2000,280:235-245. |
[5] | Kim J.M.;Jeong Y.H. .Correlation of heat treatment and corrosion behavior of Zr-Nb-Sn-Fe-Cu alloys[J].Journal of Materials Processing Technology,2000(1/2):145-149. |
[6] | 李强,刘文庆,周邦新.变形及热处理对Zr-Sn-Nb合金中β-Zr分解的影响[J].稀有金属材料与工程,2002(05):389-392. |
[7] | 刘文庆,李强,周邦新,姚美意.显微组织对ZIRLO锆合金耐腐蚀性的影响[J].核动力工程,2003(01):33-36. |
[8] | Nikulina A V;Markelov V A;Peregud M M.Zirconium alloy E635 as a material for fuel rod cladding and other components of VVER and RBMK cores[A].ASTM,Philadelphia,PA,1996:785-804. |
[9] | Mardon J P;Charquet D;Senevat J.Influence of composition and fabrication process on out-of-pile and in-pile properties of M5 alloy[A].ASTM West Conshohocken,PA,2000:505-524. |
[10] | Charquet D;Hahn R;Ortlieb.Solubility limits and formation of intermetallic precipitates in ZrSnFeCr alloys[A].ASTM,Philadelphia,PA,1989:405-422. |
[11] | Choo K N;Kang Y H;Pyum S I et al.Effect of composition and heat treatment on the microstructure and corrosion behavior of Zr-Nb alloys[J].Journal of Nuclear Materials,1994,209:226-235. |
上一张
下一张
上一张
下一张
计量
- 下载量()
- 访问量()
文章评分
- 您的评分:
-
10%
-
20%
-
30%
-
40%
-
50%