FRACTURE MECHANICS EXAMINATION OF INTEGRITY OF PRIMARY COOLANT INLET NOZZLE OF A PRESSURIZED-WATER REACTOR VESSEL FOLLOWING A POSTULATED LOSS OF COOLANT

被引：0
|
作者：
STAHLBERG, R [1 ]
机构：
[1] TECH UBERWACHUNGS VEREINS RHEINLAND EV,INST MATERIALPRUFUNG & CHEM,KOLN,FED REP GER
来源：
ARCHIV FUR DAS EISENHUTTENWESEN | 1977年 / 48卷 / 10期
关键词：
D O I：
10.1002/srin.197705064
中图分类号：
TF [冶金工业];
学科分类号：
0806 ;
摘要：
引用
下载
收藏
页码：551 / 554
页数：4
相关论文
共 50 条
  • [11] Simulation of Loss of Coolant Accident in an Integral Pressurized Water Reactor (IPWR)
    Khan, Salah Ud-Din
    Peng, Minjun
    Zubair, Muhammad
    FRONTIERS OF MANUFACTURING SCIENCE AND MEASURING TECHNOLOGY, PTS 1-3, 2011, 230-232 : 410 - 414
  • [12] SAFETY ASSESSMENT OF REACTOR PRESSURE VESSEL INTEGRITY FOR LOSS OF COOLANT ACCIDENT CONDITIONS
    Beukelmann, D.
    Guo, W.
    Holzer, W.
    Kauer, R.
    Muench, W.
    Reichel, C.
    Schoener, P.
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE 2010, VOL 7, 2010, : 339 - 348
  • [13] Safety Assessment of Reactor Pressure Vessel Integrity for Loss of Coolant Accident Conditions
    Beukelmann, Dieter
    Guo, Wenfeng
    Holzer, Wieland
    Kauer, Robert
    Muench, Wolfgang
    Reichel, Christoph
    Schoener, Peter
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2012, 134 (01):
  • [14] Structural Integrity of Reactor Pressure Vessel for Small Break Loss of Coolant Accident
    Jhung, Myung Jo
    Choi, Young Hwan
    Jang, Changheui
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2009, 46 (03) : 310 - 315
  • [15] Measurement of 90Sr in primary coolant of pressurized water reactor
    L. Lazare
    C. Crestey
    C. Bleistein
    Journal of Radioanalytical and Nuclear Chemistry, 2009, 279 : 633 - 638
  • [16] Measurement of 90Sr in primary coolant of pressurized water reactor
    Lazare, L.
    Crestey, C.
    Bleistein, C.
    JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 2009, 279 (02) : 633 - 638
  • [17] Weight optimal design of the primary coolant system for a pressurized water reactor
    Chen, Lei
    Yan, Changqi
    Wang, Jianjun
    Liu, Chengyang
    ANNALS OF NUCLEAR ENERGY, 2014, 68 : 61 - 69
  • [18] Numerical Study on Coolant Flow Distribution at the Core Inlet for an Integral Pressurized Water Reactor
    Sun, Lin
    Peng, Minjun
    Xia, Genglei
    Lv, Xing
    Li, Ren
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2017, 49 (01) : 71 - 81
  • [19] A SPACE-DEPENDENT LOSS-OF-COOLANT ACCIDENT ANALYSIS FOR PRESSURIZED-WATER NUCLEAR PLANTS
    NAHAVANDI, AN
    BORDELON, FM
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1967, 10 (02): : 703 - +
  • [20] FATIGUE GROWTH AND FRACTURE RISK FROM POSTULATED CRACKS IN PRESSURIZED-WATER REACTOR PIPING WELDS
    CHAMPOMIER, FP
    BONEH, B
    GILLES, P
    HILSENKOPF, P
    NUCLEAR ENGINEERING AND DESIGN, 1991, 129 (03) : 315 - 319
12345