Materials Reports 2020, Vol. 34 Issue (Z2): 418-422 |
METALS AND METAL MATRIX COMPOSITES |
|
|
|
|
|
Evaluation of Dynamic Fracture Toughness of Primary Pipeline Material Based on PCVN Small Sample |
LIU Erwei, JIA Wenqing, XUE Fei, FAN Minyu, YU Min, YU Weiwei
|
Suzhou Nuclear Power Research Institute, Suzhou 215004, China |
|
|
Abstract In view of the typical thermal aging phenomenon of primary coolant pipes during service in CPR1000+ unit, the influence of thermal aging time on dynamic fracture toughness of primary coolant piping materials were investigated by the 55 mm×10 mm×10 mm pre-crack impact (PCVN) sample, combined with 3D digital image correlation (DIC). The dynamic crack growth resistance curves (dynamic J-R curve) of the base metal were obtained based on the dynamic load-displacement curves by the key curve method and load separation method, and then compared with the quasi-static fracture toughness variation tendency, and it is found that, there is an obvious embrittlement in primary pipeline mate-rial after thermal aging.
|
Published: 08 January 2021
|
|
About author:: Erwei Liu received her M.S. degrees in June 2011 from Chongqing University in engineering. Since July 2011, she has worked in Suzhou Nuclear Power Research Institute, focusing on the research of material used in nuclear power plant. Weiwei Yu, Ph.D., graduated from Tianjin University,the director of the Materials & Engineering Mechanics Research branch in Suzhou Nuclear Power Research Institute. He is mainly engaged in research on thermal aging and structural integrity of nuclear power materials. |
|
|
1 Xue F, Wang Z X, Shu G G, et al. Nuclear Engineering and Design, 2009, 239,2217. 2 罗强, 王理, 刘思维,等. 钢铁研究学报, 2015, 27(10), 46. 3 王永强, 李时磊, 杨滨,等. 材料导报, 2012, 26(2),101. 4 Troshchenko V T, Prokopenko A V, Pokrovsky V V. Fatigue & Fracture of Engineering Materials & Structures, 2007, 1, 247. 5 Chandra K, Kain V, Bhutani V,et al. Materials Science and Engineering A, 2012, 534,163. 6 刘思维, 罗强, 陈勇, 等. 材料导报, 2015, 29(专辑26), 267. 7 李世伟, 余伟炜, 蒙新明, 等. 中国测试, 2014,40(5),130. 8 Li S L, Wang Y L, Wang X T, et al. Journal of Nuclear Materials, 2014, 452, 382. 9 Li S L, Wang Y L, Zhang H L, et al. Journal of Nuclear Materials, 2013, 433, 41. 10 Silva R, Baroni L F S, Silva M B R, et al. Materials Characterization, 2016, 114, 211. 11 Iturgoyen L, Anglada M. Fatigue & Fracture of Engineering Materials & Structures, 2010, 20,645. 12 薛飞, 束国刚, 余伟炜, 等.工程力学,2010,27(8),246. 13 Viehrig H W, Houska M, Kalkhof D, et al. International Journal of Pressure Vessels Piping, 2015, 135, 36. 14 O'Donnell I J, Huthmann H,Tavassoli A A. International Journal of Pressure Vessels Piping, 1996, 65, 209. 15 Chen M Y, Yu W W, Qian G A, et al. Nuclear Engineering and Design, 2016, 301, 333. 16 Kwon J D, Ihn J H, Park J C, et al. Journal of Mechanical Science and Technology, 2002, 16, 902. 17 Yagawa G,Yoshimura S. Nuclear Engineering and Design, 1986, 97, 195. 18 Zhang X P, Shi Y W. International Journal Fracture, 1996, 81,195. 19 Zhang Q B, Zhao J. International Journal Fracture, 2014, 189, 1. 20 Ren Z J, Ru C Q. Engineering Fracture and Mechanics, 2013, 99,214. 21 Palo A. Ductile fracture handbook, EPRI-NP-6301, Electric Power Research Institute, 1989. 22 Kwon J D, Ihn J H, Park J C, et al. Journal of Mechanical Science and Technology, 2002,16, 902. 23 Yu W W, Fan M Y, Gao H B, et al. Nuclear Engineering and Design, 2018, 327, 150. |
|
|
|