Low-temperature fracture mechanisms in a spheroidised reactor pressure vessel steel

被引:7
|
作者
Kumar, A. [1 ]
Roberts, S. G. [1 ]
Wilkinson, A. J. [1 ]
机构
[1] Univ Oxford, Dept Mat, Oxford OX1 3PH, England
基金
英国工程与自然科学研究理事会;
关键词
ferritic steels; fracture; low temperature deformation; brittle-ductile transitions; quasi-cleavage;
D O I
10.1007/s10704-007-9084-3
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The micromechanisms of fracture of a spheroidised A533B reactor pressure vessel steel over the temperature range of - 190 degrees C to +60 degrees C were investigated by performing uniaxial tensile tests on double-notched cylindrical specimens. Failure was by quasi-cleavage at temperatures between -190 degrees C and - 145 degrees C. Quasi-cleavage fracture surfaces are characterised by clusters of planar facets that are separated from other facets either by large voids or by clusters of microvoids. At temperatures between - 145 degrees C and -25 degrees C failure was by mixed microvoid coalescence and cleavage while complete microvoid coalescence was observed at temperatures higher than -25 degrees C. Over the whole temperature range studied, fracture nucleation was either from large single voids or localised regions of microvoids.
引用
收藏
页码:121 / 129
页数:9
相关论文
共 50 条
  • [21] FRACTURE TOUGHNESS OF HEAVY SECTION STEEL FOR NUCLEAR-REACTOR PRESSURE-VESSEL
    SUSUKIDA, H
    SUNAMOTO, D
    SATOH, M
    FUNADA, T
    TRANSACTIONS OF THE IRON AND STEEL INSTITUTE OF JAPAN, 1977, 17 (09) : 497 - 505
  • [22] Fatigue fracture features of pressure vessel steel in simulated light water reactor environment
    Lee, SG
    Kim, IS
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2001, 38 (02) : 120 - 126
  • [24] LOWER-BOUND FRACTURE-TOUGHNESS OF A REACTOR-PRESSURE-VESSEL STEEL
    ROSENFIELD, AR
    SHETTY, DK
    ENGINEERING FRACTURE MECHANICS, 1981, 14 (04) : 833 - &
  • [25] Effect of tempering temperature on the microstructure and mechanical properties of a reactor pressure vessel steel
    Li, C. W.
    Han, L. Z.
    Luo, X. M.
    Liu, Q. D.
    Gu, J. F.
    JOURNAL OF NUCLEAR MATERIALS, 2016, 477 : 246 - 256
  • [26] High temperature creep behavior of a low alloy Mn-Mo-Ni reactor pressure vessel steel
    Sarkar, Apu
    Sunil, Saurav
    Kumawat, Bhupendra
    Reddy, G. Bharat
    Kapoor, Rajeev
    Kumar, Harish
    Shrivastav, Vivek
    JOURNAL OF NUCLEAR MATERIALS, 2021, 557
  • [27] On flux effects in a low alloy steel from a Swedish reactor pressure vessel
    Boasen, Magnus
    Efsing, Pal
    Ehrnsten, Ulla
    JOURNAL OF NUCLEAR MATERIALS, 2017, 484 : 110 - 119
  • [28] On the Analysis of Clustering in an Irradiated Low Alloy Reactor Pressure Vessel Steel Weld
    Lindgren, Kristina
    Stiller, Krystyna
    Efsing, Pal
    Thuvander, Mattias
    MICROSCOPY AND MICROANALYSIS, 2017, 23 (02) : 376 - 384
  • [29] Micromechanical modelling of reactor pressure vessel steel
    Chhibber, R.
    Singh, H.
    Arora, N.
    Dutta, B. K.
    MATERIALS & DESIGN, 2012, 36 : 258 - 274
  • [30] REACTOR PRESSURE-VESSEL FUNCTIONALITY ISSUES AND THE DEVELOPMENT OF A LOW-TEMPERATURE OVERPRESSURIZATION TRANSIENT LIMIT FOR PRECLUDING CRACK INITIATION
    HIJECK, PJ
    GANTA, BR
    AYRES, DJ
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1993, 54 (1-2) : 213 - 230