The Morphology of Defects of a Weld Joints of a Drum with a Steam-Generator Housing of VVER-1000 Generator Units

被引:0
|
作者
Korneev, A. E. [1 ]
Lovchev, V. N. [2 ]
Kharina, I. L. [1 ]
Gutsev, D. F. [2 ]
机构
[1] NPO Cent Sci Res Inst Machine Bldg Technol, Moscow 115088, Russia
[2] Rosenergoatom, Moscow 109507, Russia
关键词
weld joint; crack; morphology; stress corrosion cracking;
D O I
10.1134/S2070205117070103
中图分类号
TF [冶金工业];
学科分类号
0806 ;
摘要
Results of an investigation of the morphology of cracks that form during the operation in the weld joint of a heat-carrier drum with the steam-generator housing of nuclear-power plant with a VVER-1000 unit are given. The reasons for the formation of cracks are the compound-stress state of weld units, the corrosive effect of the heat carrier, and the operating temperature. Crack formation proceeds according to the delayed stress corrosion cracking on the internal surface of metal upon contact with the corrosion medium. The features of crack formation and propagation mechanism should be considered during remedial measures that are aimed at the maintenance of the reliability of the weld joint of a drum with the steam-generator housing of VVER-1000 units.
引用
收藏
页码:1235 / 1239
页数:5
相关论文
共 50 条
  • [31] UTILITY GROUPS 1ST STEAM-GENERATOR REPLACEMENT UNITS ARE IN THE WORKS
    WALD, G
    NUCLEAR ENGINEERING INTERNATIONAL, 1993, 38 (466): : 35 - 35
  • [32] POST-WELD HEAT-TREATMENT OF TUBEPLATE WELDS ON PWR STEAM-GENERATOR
    COTTRELL, D
    METALLURGIA, 1990, 57 (03): : 145 - 145
  • [33] MECHANISM OF DAMAGE OF WELDED JOINTS OF COLLECTOR WELDING TO STEAM GENERATOR BODIES OF POWER UNITS OF WWER-1000
    Neklyudov, I. M.
    Ozhigov, L. S.
    Mitrophanov, A. S.
    Voyevodin, V. N.
    Tolstolutskay, G. D.
    Bryk, V. V.
    Ruzhitskiy, V. V.
    PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY, 2012, (02): : 40 - 45
  • [34] Computerized system for eddy-current tests of the zones between the holes in the steam generator headers at nuclear power stations with VVER-1000 reactors
    Gorbatykh, V.P.
    Morozov, A.V.
    Fedorov, A.Yu.
    Fedorov, Yu.N.
    Thermal Engineering (English translation of Teploenergetika), 1998, 45 (05):
  • [35] Life calculations for header - PGV-1000 steam generator connector weld joints under NPP service conditions
    Stepanov G.V.
    Kharchenko V.V.
    Babutskii A.I.
    Romanov S.V.
    Feofentov N.A.
    Kravchenko I.V.
    Strength of Materials, 2004, 36 (3) : 321 - 326
  • [36] A STUDY OF THE LEVELING CAPACITY OF THE IMMERSED PERFORATED PLATE IN A PGV-1000 STEAM-GENERATOR
    SAAKOV, ES
    SVISTUNOV, EP
    PIKUS, VY
    NEKRASOV, AV
    SEVASTYANOV, VP
    MUKHACHEV, VL
    TARANKOV, GA
    MOLCHANOV, VP
    THERMAL ENGINEERING, 1992, 39 (07) : 409 - 411
  • [37] STEAM-GENERATOR GRADE P91 STEEL COMPONENT WELD CREEP-ASSESSMENT
    Grisolia, Ottaviano
    Scano, Lorenzo
    Piccini, Francesco
    Lo Conte, Antonietta
    De Agostinis, Massimiliano
    Fini, Stefano
    PROCEEDINGS OF ASME 2023 PRESSURE VESSELS & PIPING CONFERENCE, PVP2023, VOL 1, 2023,
  • [38] Application of the radius system of software tools based on a PC/AT personal computer for analyzing the dynamics of a steam generator at a nuclear power station with a VVER-1000 reactor
    Dorri, M. Kh.
    Nozdrin, G.N.
    Khoze, B.S.
    Pylaev, A.M.
    Thermal Engineering (English translation of Teploenergetika), 1994, 41 (08):
  • [40] The safety improvement of VVER-1000 NPP against SBO accident using portable air-cooled diesel generator
    Jabbari, M.
    Hadad, K.
    Pirouzmand, A.
    ANNALS OF NUCLEAR ENERGY, 2020, 139