Benchmark analysis on PFM analysis codes for aged piping of nuclear power plants

被引:0
|
作者
Hiroto Itoh
Yinsheng Li
Kazuya Osakabe
Kunio Onizawa
Shinobu Yoshimura
机构
[1] Japan Nuclear Energy Safety Organization,
[2] Mizuho Information & Research Institute,undefined
[3] Japan Atomic Energy Agency,undefined
[4] The University of Tokyo,undefined
关键词
Aged piping; Benchmark analysis; Probabilistic fracture mechanics; Stress corrosion cracking;
D O I
暂无
中图分类号
学科分类号
摘要
Probabilistic fracture mechanics is a rational methodology in structural reliability evaluation and risk assessment for aged piping in nuclear power plants. Several probabilistic fracture mechanical analysis codes have been improved or developed in Japan. To verify the reliability and applicability of two of these codes, we did a benchmark analysis using their basic functions in consideration of representative piping systems in nuclear power plants and typical aging mechanisms. Based on the analysis results, we concluded that the analysis results of these two codes are in good agreement.
引用
收藏
页码:2055 / 2058
页数:3
相关论文
共 50 条
  • [21] EVALUATION OF AGED STEAM PIPING MAKES FOR SAFER POWER-PLANTS
    WRAY, R
    BALASCHAK, JJ
    POWER ENGINEERING, 1987, 91 (08) : 26 - 30
  • [22] EVALUATION OF AGED STEAM PIPING MAKES FOR SAFER POWER PLANTS.
    Wray, Ron
    Balaschak, James J.
    Power Engineering (Barrington, Illinois), 1987, 91 (08): : 26 - 30
  • [23] ACCIDENT ANALYSIS OF NUCLEAR-POWER PLANTS
    KUNZE, B
    EICHHORN, H
    KERNENERGIE, 1973, 16 (11): : 333 - 336
  • [24] Anomaly Detection and Analysis in Nuclear Power Plants
    Chaudhary, Abhishek
    Han, Junseo
    Kim, Seongah
    Kim, Aram
    Choi, Sunoh
    ELECTRONICS, 2024, 13 (22)
  • [25] Sensitivity analysis for the outages of nuclear power plants
    Barty, Kengy
    Bonnans, J. Frederic
    Pfeiffer, Laurent
    ENERGY SYSTEMS-OPTIMIZATION MODELING SIMULATION AND ECONOMIC ASPECTS, 2014, 5 (02): : 371 - 406
  • [26] A Benchmark-based Approach for the Validation of Eddy Current Simulation Codes in Support of Nuclear Power Plants Inspection
    Mayos, Michel
    Moreau, Olivier
    Costan, Valentin
    Gilles-Pascaud, Catherine
    Reboud, Christophe
    Buvat, Fabrice
    ELECTROMAGNETIC NONDESTRUCTIVE EVALUATION (XIII), 2010, 33 : 191 - 198
  • [27] Severe Accident Analysis in Nuclear Power Plants
    Espinosa-Paredes, Gilberto
    Batet, Lluis
    Nunez-Carrera, Alejandro
    Sugimoto, Jun
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2012, 2012
  • [28] Precursor analysis for German nuclear power plants
    Babst, S
    Hörtner, H
    Stück, R
    SAFETY AND RELIABILITY, VOLS 1 & 2, 1999, : 1517 - 1522
  • [29] Probabilistic fracture mechanics analysis of thermally aged nuclear piping in a pressurized water reactor
    Li, Shuxiao
    Zhang, Hailong
    Li, Shilei
    Wang, Yanli
    Xue, Fei
    Wang, Xitao
    NUCLEAR ENGINEERING AND DESIGN, 2013, 265 : 611 - 618
  • [30] Ageing Analysis of Power Cables used in Nuclear Power Plants
    Abro, Shahid Hussain
    Shah, Syed Aqeel Ahmed
    Alaboodi, Abdulaziz Solaiman
    Shoaib, Talha
    MEHRAN UNIVERSITY RESEARCH JOURNAL OF ENGINEERING AND TECHNOLOGY, 2020, 39 (01) : 195 - 204