THE CHARACTERISTICS OF VISCOPLASTIC EFFECTS IN DYNAMIC CRACK-PROPAGATION IN NUCLEAR-REACTOR PRESSURE-VESSEL STEELS

被引:0
|
作者
POPELAR, CH [1 ]
SHEU, YC [1 ]
机构
[1] MODERN ENGN SERV,WARREN,MI 48092
关键词
D O I
10.1016/0029-5493(92)90166-S
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A small-scale yielding analysis is performed for steady state, rapid crack propagation in order to quantify the influence of viscoplasticity in A533B steel. The Bodner-Partom viscoplastic model is used in this analysis. Because the elastic strain rate dominate the viscoplastic strain rates near the crack tip, an inverse square root singularity in the stress exists at the tip. Estimates for the strength of the crack-tip field in terms of the strength of the remote elastic field and the material properties of the A533B steel are established. The plastic shielding is sufficient to reduce the strength of the crack-tip field to an order of magnitude smaller than that of the remote field. A finite-element analysis is also performed to establish the size of the zone of dominance for the crack-tip field. The crack-tip zone of dominance is typically several orders of magnitude smaller than the extent of the plastic zone. Aside from posing rather severe finite-element modeling problems, this large disparity brings into thc question the relevance of the crack-tip region when compared to the size of the fracture process zone.
引用
收藏
页码:411 / 418
页数:8
相关论文
共 50 条
  • [1] TRANSIENT FINITE-ELEMENT CRACK-PROPAGATION MODEL FOR NUCLEAR PRESSURE-VESSEL STEELS
    KEEGSTRA, PNR
    JOURNAL OF THE INSTITUTION OF NUCLEAR ENGINEERS, 1976, 17 (04): : 89 - 96
  • [2] ON THE MECHANISMS OF ENVIRONMENT SENSITIVE CYCLIC CRACK-GROWTH OF NUCLEAR-REACTOR PRESSURE-VESSEL STEELS
    HANNINEN, H
    TORRONEN, K
    KEMPPAINEN, M
    SALONEN, S
    CORROSION SCIENCE, 1983, 23 (06) : 663 - &
  • [3] VISCOPLASTIC MODELING OF DYNAMIC FRACTURE EVENTS IN REACTOR PRESSURE-VESSEL STEELS
    BASS, BR
    KEENEYWALKER, J
    CHANG, SJ
    PARROT, JS
    PUGH, CE
    HORNBERGER, K
    SCHWARTZ, CW
    NUCLEAR ENGINEERING AND DESIGN, 1992, 133 (03) : 419 - 431
  • [4] POSITRON-ANNIHILATION MEASUREMENTS ON NUCLEAR-REACTOR PRESSURE-VESSEL STEELS
    VANHOOREBEKE, L
    VANDEVELDE, J
    SEGERS, D
    DORIKENSVANPRAET, L
    SIMULA, S
    JOURNAL DE PHYSIQUE IV, 1995, 5 (C1): : 171 - 175
  • [5] FATIGUE CRACK-PROPAGATION IN NEUTRON-IRRADIATED FERRITIC PRESSURE-VESSEL STEELS
    JAMES, LA
    NUCLEAR SAFETY, 1977, 18 (06): : 791 - 801
  • [6] A STUDY OF FATIGUE CRACK-PROPAGATION IN PRIOR HYDROGEN ATTACKED PRESSURE-VESSEL STEELS
    PENDSE, RD
    RITCHIE, RO
    METALLURGICAL TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 1985, 16 (08): : 1491 - 1501
  • [7] ON THE USE OF COUPLED PRESSURE BARS TO MEASURE THE DYNAMIC FRACTURE INITIATION AND CRACK-PROPAGATION TOUGHNESS OF PRESSURE-VESSEL STEELS
    COUQUE, H
    HUDAK, SJ
    LINDHOLM, US
    JOURNAL DE PHYSIQUE, 1988, 49 (C-3): : 347 - 353
  • [8] STRESS-CORROSION CRACKING OF NUCLEAR-REACTOR PRESSURE-VESSEL AND PIPING STEELS
    SPEIDEL, MO
    MAGDOWSKI, RM
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1988, 34 (1-5) : 119 - 142
  • [9] AN ANALYSIS OF DYNAMIC CRACK-PROPAGATION AND ARREST IN A NUCLEAR PRESSURE-VESSEL UNDER THERMAL-SHOCK CONDITIONS
    JUNG, J
    KANNINEN, MF
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 1983, 105 (02): : 111 - 116
  • [10] FRACTOGRAPHY IN EVALUATION OF THE MECHANISM OF ENVIRONMENT-SENSITIVE CYCLIC CRACK-GROWTH OF NUCLEAR-REACTOR PRESSURE-VESSEL STEELS
    KEMPPAINEN, H
    HANNINEN, H
    TORRONEN, K
    SALONEN, S
    ULTRAMICROSCOPY, 1982, 9 (04) : 396 - 397