|
|
辐照后N18锆合金氢致延迟开裂临界温度预测 |
孙超1), 谭军2), 应诗浩1), 李聪3), 彭倩1), 赵素琼1) |
1) 中国核动力研究设计院核燃料及材料国家级重点实验室, 成都 610041
2) 中国工程物理研究院核物理与化学研究所, 绵阳 621900
3) 国家核电技术公司科研部, 北京 100140 |
|
PREDICTION OF CRITICAL TEMPERATURE FOR DELAYED HYDRIDE CRACKING IN IRRADIATED N18 ZIRCONIUM ALLOY |
SUN Chao1), TAN Jun2), YING Shihao1), LI Cong3), PENG Qian1), ZHAO Suqiong1) |
1) National Key Laboratory for Nuclear Fuel and Materials, Nuclear Power Institute of China, Chengdu 610041
2) Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900
3) Dept. of R$\&$D, State Nuclear Power Technology Corp., Ltd. Beijing 100140 |
引用本文:
孙超 谭军 应诗浩 李聪 彭倩 赵素琼. 辐照后N18锆合金氢致延迟开裂临界温度预测[J]. 金属学报, 2010, 46(7): 805-809.
,
,
,
,
,
.
PREDICTION OF CRITICAL TEMPERATURE FOR DELAYED HYDRIDE CRACKING IN IRRADIATED N18 ZIRCONIUM ALLOY[J]. Acta Metall Sin, 2010, 46(7): 805-809.
[1] Chu W Y. Hydrogen Damage and Delayed Fracture. Beijing: Metallurgical Industry Press, 1988: 189
(褚武扬. H损伤及滞后断裂. 北京: 冶金工业出版社, 1988: 189)
[2] Matsui H, Yoshikawa N, Koiwa M. Acta Metall, 1987; 35: 413
[3] Cann C D, Sexton E E. Acta Metall, 1980; 28: 1215
[4] Pan C, Li Z B, Liang D T, Tian Z L, Chu W Y, Qiao L J. Acta Metall Sin, 2001; 37: 296
(潘川, 李正邦, 梁东图, 田志凌, 褚武扬, 乔利杰. 金属学报, 2001; 37: 296)
[5] Gao K W, Wang Y B, Qiao L J, Chu W Y. Sci China, 1999; 29E: 289
(高克玮, 王燕斌, 乔利杰, 褚武扬. 中国科学, 1999; 29E: 289)
[6] Dutton R, Nuttall K, Puls M P, Simpson L A. Metall Trans, 1977; 8A: 1553
[7] Shi S Q, Puls M P. J Nucl Mater, 1994; 208: 232
[8] Shi S Q, Shek G K, Puls M P. J Nucl Mater, 1995; 218: 189
[9] Yang W D. Nuclear Reactor Material. Beijing: Atom Energy Press, 2000: 277
(杨文斗. 反应堆材料学. 北京: 原子能出版社, 2000: 277)
[10] Perryman E C W. Nucl Energy, 1978; 17: 95
[11] Efsing P, Pettersson K. Zirconium in the Nuclear Industry: 12th International Symposium, West Conshohocken: ASTM International, 2000: 340
[12] Viatcheslav G, Robert J. J ASTM Int, 2005; 2: 711
[13] Schofield J S, Edward C D, Gee C F. Zirconium in the Nuclear Industry: 13th International Symposium, West Conshohocken: ASTM International, 2002: 339
[14] Liu Y Z, Zu X T, Qiu S Y, Li C, Ma W G, Huang X Q. Surf Coat Technol, 2006; 200: 5631
[15] ZhaoWJ, Liu Y Z, Jiang H M, Peng Q. J Alloys Compd, 2008; 462: 103
[16] Tan J, Ying S H, Li C, Sun C. Scr Mater, 2006; 55: 513
[17] Sun C, Tan J, Ying S H, Li C, Peng Q, Zhao S Q. Acta Metall Sin, 2009; 5: 541
(孙超, 谭军, 应诗浩, 李聪, 彭倩, 赵素琼. 金属学报, 2009; 5: 541)
[18] Tang J R. Chin J Nuclear Sci Eng, 2003; 23: 266
(唐炯然. 核科学与工程, 2003; 23: 266)
[19] Liu J Z. Nuclear Structure Materials. Beijing: Chemistry Industry Press, 2007: 143
(刘建章. 核结构材料. 北京: 化学工业出版社, 2007: 143)
[20] Une K, Ishimoto S. J Nucl Mater, 2003; 322: 66
[21] McMinn A, Edward C D, Schofield J S. Zirconium in the Nuclear Industry: 12th International Symposium, West Conshohocken: ASTM International, 2000: 173
[22] Li J C M, Oriani R A, Darken L S. Z Phys Chem, 1966; 49: 271 |
|
Viewed |
|
|
|
Full text
|
|
|
|
|
Abstract
|
|
|
|
|
Cited |
|
|
|
|
|
Shared |
|
|
|
|
|
Discussed |
|
|
|
|