Erosion-corrosion wear of the components of pipeline systems at nuclear power stations equipped with RBMK-1000 reactors

被引：0
|
作者：
Baranenko V.I. [1 ]
Yanchenko Yu.A. [1 ]
机构：
[1] All-Russia Institute for Nuclear Power Plant Research, Moscow, 109507
来源：
Thermal Engineering | 2010年 / 57卷 / 5期
关键词：
Corrosion Product; Weld Zone; Nuclear Power Station; Corrosion Wear; Pipeline System;
D O I：
10.1134/S0040601510050058
中图分类号：
学科分类号：
摘要：
The erosion-corrosion wear of components of pipeline systems at nuclear power stations equipped with RBMK-1000 reactors is analyzed. It is shown that the mechanism of erosion-corrosion wear involves two parallel processes: thinning of pipeline walls in some sections and sedimentation of corrosion products in the other sections. © Pleiades Publishing, Inc., 2010.
引用
收藏
页码：391 / 399
页数：8
相关论文
共 45 条
  • [31] EROSION-CORROSION WEAR OF A METAL IN THE ENTRANCE SECTIONS OF HEATER COILS IN NUCLEAR-POWER-PLANTS
    BARANENKO, VI
    KIROV, VS
    KRAVCHENKO, VP
    DAVIDENKO, NN
    SHALAEV, AG
    FEDOROV, YN
    VORONTSOV, EO
    ERMOLAEV, EO
    PESTRIKOV, AF
    ZAKHAROV, VA
    ATOMIC ENERGY, 1995, 78 (02) : 81 - 85
  • [32] Increasing the rated capacity of power units installed at Russian nuclear power stations equipped with VVER-1000 reactors
    Ignatov V.I.
    Shutikov A.V.
    Ryzhkov Yu.A.
    Kop'Ev Yu.V.
    Ryzhov S.B.
    Berkovich V.Ya.
    Semchenkov Yu.M.
    Aminov R.Z.
    Khrustalev V.A.
    Thermal Engineering, 2009, 56 (11) : 963 - 966
  • [33] Solving the problems of erosion-corrosion wear of equipment and pipelines in nuclear power plants: Domestic and international experience
    Baranenko V.I.
    Yanchenko Yu.A.
    Thermal Engineering, 2007, 54 (5) : 348 - 355
  • [34] Development of software tools for calculating corrosion-erosion wear of pipelines at nuclear power stations
    Baranenko V.I.
    Kumov A.V.
    Yanchenko Yu.A.
    Prokopenko A.S.
    Thermal Engineering, 2007, 54 (12) : 981 - 988
  • [35] Specific features of corrosion damage to heat-transfer tubes of steam generators used at nuclear power stations equipped with VVER-1000 reactors
    Nemytov D.S.
    Tyapkov V.F.
    Thermal Engineering, 2009, 56 (7) : 612 - 616
  • [36] Assessing the influence of uncertain factors in analyzing emergency processes at nuclear power stations equipped with VVER-1000 reactors
    Vorob'ev Yu.B.
    Kuznetsov V.D.
    Mansuri M.
    Thermal Engineering, 2006, 53 (09) : 688 - 693
  • [37] Predicting local distributions of erosion-corrosion wear sites for the piping in the nuclear power plant using CFD models
    Ferng, Y. M.
    ANNALS OF NUCLEAR ENERGY, 2008, 35 (02) : 304 - 313
  • [38] The introduction of precoat ion-exchange filtration in special water-treatment plants at operating RBMK-1000 reactor-based nuclear power stations
    Tyapkov, V.F.
    Chudakova, I.Yu.
    Tishkov, V.M.
    Yatsko, O.V.
    Thermal Engineering, 2005, 52 (07) : 556 - 561
  • [39] EMPLOYMENT OF NUCLEAR-POWER STATIONS WITH VVER-1000 REACTORS IN HEAT-SUPPLY SYSTEMS
    DLUGOSELSKII, VI
    VARVARSKII, VS
    GRIBOV, VB
    THERMAL ENGINEERING, 1985, 32 (12) : 657 - 660
  • [40] PRELIMINARY EXPERIMENTAL STUDY ON EROSION-CORROSION BEHAVIOR OF SECOND LOOP PIPELINE IN NUCLEAR POWER PLANT WITH VAPOR LIQUID TWO PHASE FLOW
    Liu, Pengfei
    Zhang, Xian
    Zhao, Nan
    Liu, Junliang
    Kuang, Bo
    PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 6, 2017,
12345