Effect of temperature on the microscopic appearance of the fracture surface of alloy 690TT under SSRT testing

被引:2
|
作者
Ito, Yuzuru
Lu, Zhanpeng
Miura, Hideo
Yonezawa, Toshio
Shoji, Tetsuo
机构
[1] Tohoku Univ, Grad Sch Engn, Aoba Ku, Sendai, Miyagi 9808579, Japan
[2] Tohoku Univ, Fracture & Reliabil Res Inst, Aoba Ku, Sendai, Miyagi 9808579, Japan
关键词
strength; reliability; fracture surface analysis; material testing; ductile fracture; alloy; 690;
D O I
10.1299/jsmea.49.355
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
Brown, C.M. and Mills, W.J. reported that Alloy 690, a nickel based high chromium alloy, exhibited a considerable reduction in fracture toughness below 149 degrees C in hydrogenated water environments, and they proposed that the possible mechanism attributable to the toughness degradation was hydrogen-induced intergranular cracking. Based on experimental results of the compositional analysis of the fracture surface using energy dispersive x-ray spectrometry (EDS), Brown, C.M. et al. also reported that the cracks might have propagated in the matrix, very close to the grain boundary. The authors, however, had reported that intergranular cracking was confirmed in Alloy 690TT under a Slow Strain Rate Tensile (SSRT) test of a cathodically hydrogen-charged specimen. The objective of this study is to clarify the effect of temperature and hydrogen on the intergranular cracking of Alloy 690TT. Slow Strain Rate Tensile (SSRT) tests were performed at several temperatures in simulated Pressurized Water Reactor (PWR) primary water conditions and at room temperature in air. The appearance of the fracture surface after SSRT tests at about 50 degrees C showed "ductile intergranular fracture" which is characterized by the appearance of intergranular cracks on the fracture surface accompanied by dimples. No great difference was observed between the maximum stress after a SSRT test at 320 degrees C in simulated PWR primary water conditions and a tensile test at room temperature in air. In addition, no correlation was found between the appearance of the fracture surface after either the SSRT or tensile tests and the test conditions such as strain rate and the amount of dissolved hydrogen in the water. Brown, C.M. et al. observed hydrogen-induced intergranular cracking with a CT specimen where the crack penetrates through the high tri-axial stress field, while in this paper we observed ductile intergranular fracture with smooth SSRT specimens which represent a typical uni-axial stress state. Hydrogen, however, could be trapped in the high tri-axial stress state region where high stress, high strain and a high dislocation density coexist. Further experiments, including the high tri-axial stress of such cracks are needed in order to clarify in detail the mechanism for ductile intergranular fracture.
引用
收藏
页码:355 / 362
页数:8
相关论文
共 50 条
  • [1] Effect of Applied Potential and Inhibitors on PbSCC of Alloy 690TT
    Capell, Brent
    Lumsden, Jesse
    Calabrese, Michael
    Eaker, Rick
    PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, 2018, : 1129 - 1144
  • [2] Effect of Surface Scratch on Corrosion Behavior of Alloy 690TT Heat Exchanger Tubes
    Meng F.
    Wu B.
    Lv Y.
    Ming H.
    Bao Y.
    Wang J.
    Han E.-H.
    Cailiao Yanjiu Xuebao/Chinese Journal of Materials Research, 2021, 35 (11): : 827 - 834
  • [3] Effect of stress and surface finish on Pb-caustic SCC of alloy 690TT
    Mazzei, G. B.
    Burke, M. G.
    Horner, D. A.
    Scenini, F.
    CORROSION SCIENCE, 2021, 187
  • [4] Effect of temperature on corrosion fatigue behavior of Inconel Alloy 690TT steam generator tube
    Li, Z. H.
    Lu, Y. H.
    You, L.
    Zhang, X. F.
    Wang, L.
    Tian, D. H.
    Zhang, W. D.
    Shoji, T.
    CORROSION SCIENCE, 2024, 227
  • [5] Size effect of scratches on the degradation behavior of alloy 690TT in high temperature caustic solution
    Wang, X. Y.
    Li, Z. H.
    Bai, Y. K.
    Cao, X. Y.
    Liu, T. G.
    Lu, Y. H.
    Shoji, T.
    CORROSION SCIENCE, 2021, 182
  • [6] Oxide properties of deformed Alloy 690TT in caustic solution at high temperature
    Wang, X. Y.
    Li, Z. H.
    Bai, Y. K.
    Sun, C.
    Wang, K.
    Liu, T. G.
    Lu, Y. H.
    Shoji, T.
    CORROSION SCIENCE, 2020, 174 (174)
  • [7] Effect of normal force on fretting wear behavior and mechanism of Alloy 690TT in high temperature water
    Xin, L.
    Yang, B. B.
    Wang, Z. H.
    Li, J.
    Lu, Y. H.
    Shoji, T.
    WEAR, 2016, 368 : 210 - 218
  • [8] Study on the SCC behavior induced by creep cavities on scratched surface of Alloy 690TT in high temperature water
    Wang, X. Y.
    Shang, C. G.
    Li, Z. H.
    Bai, Y. K.
    Liu, T. G.
    Lu, Y. H.
    Shoji, T.
    CORROSION SCIENCE, 2022, 196
  • [9] Microstructural characteristics of Alloy 690TT subjected to fretting corrosion in high temperature water
    Xin, Long
    Yang, Beibei
    Li, Jie
    Lu, Yonghao
    Shoji, Tetsuo
    CORROSION SCIENCE, 2017, 123 : 116 - 128
  • [10] Influence of surface roughness on the corrosion behavior of Alloy 690TT in PWR primary water
    Seo, Myung Ji
    Shim, Hee-Sang
    Kim, Kyung Mo
    Hong, Sun-Ig
    Hur, Do Haeng
    NUCLEAR ENGINEERING AND DESIGN, 2014, 280 : 62 - 68