Evaluation of piping damage in German nuclear power plants

被引:5
|
作者
Bieniussa, KW
Reck, H
机构
关键词
D O I
10.1016/S0029-5493(96)01312-X
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
Information relating to piping damage in safety-relevant systems in German nuclear power plants with light water reactors (both pressurized water reactors (PWRs) and boiling water reactors (BWRs)) were analyzed with respect to the modes and the causes of damages. In general, the total range of observed piping damage is low. The incidents (82) in plants with PWRs affected mainly pipes with small diameters. Almost all damaged piping showed wall-penetrating cracks combined with leakages, which revealed the damage. Initial cracks at piping with larger diameters were discovered in isolated cases during in-service inspections. With regard to the incidents (71) in plants with BWRs, piping with small as well as large diameters was affected to different degrees. Wall-penetrating cracks combined with leakages were detected at piping with small diameters. For large-diameters pipes, cracks were indicated during in-service inspections and supplementary examinations. The results of the incident evaluations confirm the conservativeness of the safety concept chosen for the design of German nuclear power plants with light water reactors. (C) 1997 Elsevier Science Ireland Ltd.
引用
收藏
页码:15 / 32
页数:18
相关论文
共 50 条
  • [1] PIPING PENETRATIONS FOR NUCLEAR POWER PLANTS.
    Purdy, D.C.
    Bacharier, J.
    Berzak, N.
    HPAC Heating, Piping, Air Conditioning, 1975, 47 (04): : 49 - 55
  • [2] Effective technology of preventive measures against piping damage on steam lines in nuclear power plants
    Aritomi, Masanori
    Takata, Toshinori
    Morii, Takayuki
    Nihon Kikai Gakkai Ronbunshu, B Hen/Transactions of the Japan Society of Mechanical Engineers, Part B, 2011, 77 (776): : 944 - 948
  • [3] FRAGILITY OF PRIMARY PIPING OF NUCLEAR-POWER PLANTS
    SCHUELLER, GI
    HAMPL, NC
    PRADLWARTER, HJ
    NUCLEAR ENGINEERING AND DESIGN, 1988, 110 (02) : 221 - 227
  • [4] INTEGRITY CONCEPT FOR PIPING SYSTEMS WITH CORRESPONDING LEAK AND BREAK POSTULATES IN GERMAN NUCLEAR POWER PLANTS
    Ilg, Ulf y
    Nagel, Gerhard
    Koenig, Goenter
    Schuemann, Dirk
    Mayinger, Wolfgang
    Widera, Martin
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, PVP 2011, VOL 6, A AND B, 2012, : 323 - 337
  • [5] STOCHASTIC EVALUATION OF THE DYNAMIC RESPONSE AND THE CUMULATIVE DAMAGE OF NUCLEAR POWER PLANT PIPING.
    Suzuki, Kohei
    Aoki, Shigeru
    Hanaoka, Masaaki
    Memoirs of Faculty of Technology, Tokyo Metropolitan University, 1980, (30): : 2879 - 2896
  • [6] ADDRESSING THE CHALLENGE OF INSPECTING BURIED NUCLEAR PIPING IN NUCLEAR POWER PLANTS
    Angell, Peter
    Wang, Sheng-Hui
    Simon, Phil
    Kleinfelder, Hank
    Garrity, Kevin
    Sisk, Elizabeth
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, PVP 2012, VOL 1, 2012, : 291 - 297
  • [7] STRENGTH ASSESSMENT OF EQUIPMENTS AND PIPING OF WWER NUCLEAR POWER PLANTS
    Vejvoda, Stanislav
    ASME PRESSURE VESSELS AND PIPING CONFERENCE 2009, VOL 1: CODES AND STANDARDS, 2010, : 537 - 541
  • [8] Forest damage and nuclear power plants
    Hillerbrand, M.
    Martin, J.
    Muh, H.
    Atw. Atomwirtschaft, Atomtechnik, 1985, 30 (02): : 92 - 96
  • [9] COMPLEX LOW-CYCLE FATIGUE DAMAGE ASSESSMENT OF COMPONENTS AND PIPING OF NUCLEAR POWER PLANTS TYPE WWER
    Vlcek, Libor
    Junek, Lubomir
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2017, VOL 1A, 2017,
  • [10] Evaluation of LBB characteristics of candidate materials for main steam line piping in Korea nuclear power plants
    Hong, Seokmin
    Kim, Jongmin
    Kim, Maan-Won
    Kim, Hong-Deok
    Lee, Bong-Sang
    Kim, Min-Chul
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2020, 188