[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.
|