Influence of straightening process on tension properties of 690 alloy heat exchange tube used in steam generator
Received date: 2016-07-10
Online published: 2018-06-28
王永东, 蔡志刚, 杨义忠, 苏诚, 闫生志, 曹萍 . 矫直工艺对蒸汽发生器690合金传热管拉伸性能的影响[J]. 上海大学学报(自然科学版), 2018 , 24(3) : 430 -436 . DOI: 10.12066/j.issn.1007-2861.1829
Influences of straightening process and thermal treatment on the tension properties of 690 alloy tube used in steam generators were investigated. The following influence rules have been revealed. Straightening can significantly increase the room temperature yield strength of the tube, but has little effect on tensile strength. Straightening pressure has a great influence on yield strength, while straightening speed has less impact. A higher straightening pressure makes a larger increment of yield strength. Tension property of the tube after straightening can be predicted according to the test results. The process of straightening has been shown to be stable.
| [1] | 孙汉虹. 第三代核电技术AP1000[M]. 北京: 中国电力出版社, 2010: 191-192. |
| [2] | 徐勇, 程先华. 钢管压扁矫正残余应力分析[J]. 上海交通大学学报(自然科学版), 2003,37(10):1526-1528. |
| [3] | 李连进, 胡广大. 无缝钢管定径过程中的压下量和温度对残余应力分布的影响[J]. 塑性工程学报, 2007,14(5):111-115. |
| [4] | Widmark M, Melander A, Meurling F. Low cycle constant amplitude fully reversed strain controlled testing of low carbon and stainless sheet steels for simulation of straightening operations[J]. International Journal of Fatigue, 2000,22(4):307-317. |
| [5] | Diano P, Muggeo A, Van Duysen J C, et al. Relationship between microstructure and mechanical properties of Alloy 690 tubes for steam generators[J]. Journal of Nuclear Materials, 1989,168(3):290-294. |
| [6] | Little M. Alloy 690 steam generator tubing specification sourcebook [R]. 3002003124. Palo Alto, CA: EPRI, 2014: 2-8. |
| [7] | AFCEN. RCC-M. Design and construction rules for mechanical components of PWR nuclear power plants[S]. Paris: AFCEN, 2007. |
| [8] | Fukugen M. 钢管斜辊矫直的变形理论[ C]// 第三届国际轧钢会议论文集. 1985: 410-416. |
| [9] | 侍新琳, 刘软. 变形程度对位错组态演化的影响[J]. 沈阳航空工业学院学报, 2001,18(4):11-12. |
| [10] | 韩豫, 陈学东, 刘全坤, 等. 奥氏体不锈钢应变强化工艺及性能研究[J]. 机械工程学报, 2012,48(2):87-92. |
| [11] | Mcllree A R. Proceedings: 1989 EPRI alloy 690 workshop [R]. Stress corrosion nuclear steam generators/Inconel alloys tubes, NP-6750-SD. Mclean, Virginia: Dominion Engineering, Inc. 1990: 2-14. |
| [12] | 刘延光, 夏爽, 茹祥坤, 等. 利用EBSD技术分析低应变量形变显微组织[J]. 电子显微学报, 2011,30(4/5):408-413. |
/
| 〈 |
|
〉 |