Observations on sensitivity of RPV integrity probabilistic fracture mechanics evaluations to input parameters

被引:0
|
作者
Hiser, AL [1 ]
Sheng, SCF [1 ]
Malik, SN [1 ]
机构
[1] US Nucl Regulatory Commiss, Mat & Chem Engn Branch, Washington, DC 20555 USA
关键词
D O I
暂无
中图分类号
TF [冶金工业];
学科分类号
0806 ;
摘要
引用
收藏
页码:803 / 810
页数:8
相关论文
共 36 条
  • [1] Improvements to a probabilistic fracture mechanics code for evaluating the integrity of a RPV under transient loading
    Li, YS
    Kato, D
    Shibata, K
    Onizawa, K
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2001, 78 (04) : 271 - 282
  • [3] A probabilistic fracture mechanics analysis for PTS evaluation of Kori unit 1 RPV
    Jung, S.G.
    Kim, H.S.
    Jin, T.E.
    Jang, C.H.
    Jeong, I.S.
    American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP, 2000, 403 : 131 - 135
  • [4] Development of RPV reliability analysis code based on probabilistic fracture mechanics methodology
    Shibata, K
    Kato, D
    Li, YS
    JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 2001, 43 (04): : 387 - 396
  • [5] Comparison of sensitivity measures in probabilistic fracture mechanics
    Heckmann, Klaus
    Alzbutas, Robertas
    Wang, Min
    Jevremovic, Tatjana
    Lydell, Bengt O. Y.
    Sievers, Jurgen
    Duan, Xinjian
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2021, 192
  • [6] Recent Japanese probabilistic fracture mechanics researches related to failure probability of aged RPV
    Shibata, Katsuyuki
    Kanto, Yasuhiro
    Yoshimura, Shinobu
    Yagawa, Genki
    SAFETY AND STRUCTURAL INTEGRITY 2006, 2007, 120 : 49 - +
  • [7] The use of probabilistic fracture mechanics in support of deterministic assessments of structural integrity
    Wilson, R
    LIFETIME MANAGEMENT AND EVALUATION OF PLANT, STRUCTURES AND COMPONENTS, 1998, : 517 - 524
  • [8] Probabilistic Fracture Mechanics Analyses for Structural Integrity Assessment of Nuclear Components
    Garrido, O. Costa
    Niffenegger, M.
    Mora, D. F.
    Mukin, R.
    28TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE (NENE 2019), 2019,
  • [9] Sensitivity analysis of input parameters for pressure tube integrity evaluation
    Kwak, SL
    Lee, JS
    Kim, YJ
    Park, YW
    NUCLEAR ENGINEERING AND DESIGN, 2005, 235 (17-19) : 1909 - 1918
  • [10] BOILING WATER REACTOR PRESSURE VESSEL INTEGRITY EVALUATION BY PROBABILISTIC FRACTURE MECHANICS
    Chen, Bo-Yi
    Huang, Chin-Cheng
    Chou, Hsoung-Wei
    Liu, Ru-Feng
    Lin, Hsien-Chou
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE 2010, VOL 7, 2010, : 149 - 155