A Risk-Informed Approach to Leak-Before-Break Assessment of Pressure Tubes in CANDU Reactors

被引:3
|
作者
Pandey, M. D. [1 ]
Sahoo, A. K. [1 ]
机构
[1] Univ Waterloo, Dept Civil & Environm Engn, Waterloo, ON N2L 3G1, Canada
基金
加拿大自然科学与工程研究理事会;
关键词
CANDU reactor; risk-informed approach; pressure tube; delayed hydride cracking; rupture; leak-before-break; break-before-leak; reliability index; partial factors; RELIABILITY-BASED DESIGN; LOAD;
D O I
10.1115/1.3148087
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
The leak-before-break (LBB) assessment of pressure tubes is intended to demonstrate that in the event of through-wall cracking of the tube, there will be sufficient time followed by the leak detection, for a controlled shutdown of the reactor prior to the rupture of the pressure tube. CSA Standard N285.8 (2005, "Technical Requirements for In-Service Evaluation of Zirconium Alloy Pressure Tubes in CANDU Reactors," Canadian Standards Association) has specified deterministic and probabilistic methods for LBB assessment. Although the deterministic method is simple, the associated degree of conservatism is not quantified and it does not provide a risk-informed basis for the fitness for service assessment. On the other hand, full probabilistic methods based on simulations require excessive amount of information and computation time, making them impractical for routine LBB assessment work. This paper presents an innovative, semiprobabilistic method that bridges the gap between a simple deterministic analysis and complex simulations. In the proposed method, a deterministic criterion of CSA Standard N285.8 is calibrated to specified target probabilities of pressure tube rupture based on the concept of partial factors. This paper also highlights the conservatism associated with the current CSA Standard. The main advantage of the proposed approach is that it retains the simplicity of the deterministic method, yet it provides a practical, risk-informed basis for LBB assessment.
引用
收藏
页码:0214031 / 0214038
页数:8
相关论文
共 50 条
  • [31] ANALYTICAL AND NUMERICAL CRACK-GROWTH PREDICTION FOR A LEAK-BEFORE-BREAK ASSESSMENT OF A NUCLEAR PRESSURE-VESSEL
    SCHMITT, W
    NAGEL, G
    OCKEWITZ, A
    HODULAK, L
    BLAUEL, JG
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1990, 43 (1-3) : 255 - 271
  • [32] LEAK-BEFORE-BREAK EXPERIMENTS ON HEAT-TREATED ZR-2.5 WT-PERCENT NB PRESSURE TUBES
    KOIKE, MH
    TAKAHASHI, T
    BABA, H
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1990, 43 (1-3) : 39 - 56
  • [33] LEAK BEFORE BREAK CRITERION OF HIGH-PRESSURE REACTORS FOR PRODUCTION
    IWADATE, T
    TETSU TO HAGANE-JOURNAL OF THE IRON AND STEEL INSTITUTE OF JAPAN, 1986, 72 (13): : 1488 - 1488
  • [34] Seismic loads for crack stability assessment, in a review of leak-before-break (LBB) applicability
    Machida, H
    Yamashita, N
    Yoshimura, S
    Yagawa, G
    NUCLEAR ENGINEERING AND DESIGN, 2005, 235 (01) : 21 - 31
  • [35] COMPARISON OF LEAK-BEFORE-BREAK ASSESSMENT OF MAIN LOOP PIPING LINES FABRICATED OF DIFFERENT MATERIALS
    Ma, Linwei
    Zheng, Xiaotao
    Wang, Yan
    He, Jiasheng
    Shu, Anqing
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2016, VOL 6A, 2017,
  • [36] Fracture mechanics assessment of thermal aged nuclear piping based on the Leak-Before-Break concept
    Chen, Mingya
    Yu, Weiwei
    Qian, Guian
    Wang, Rongshan
    Lu, Feng
    Zhang, Guodong
    Xue, Fei
    Chen, Zhilin
    NUCLEAR ENGINEERING AND DESIGN, 2016, 301 : 333 - 340
  • [37] Comparison of Leak-Before-Break Assessment of Main Loop Piping Lines Fabricated of Different Materials
    Ma, Linwei
    He, Jiasheng
    Shu, Anqing
    Zheng, Xiaotao
    Xu, Jianmin
    Yu, Jiuyang
    Hedongli Gongcheng/Nuclear Power Engineering, 2017, 38 (05): : 49 - 53
  • [38] The effect of characteristic crack sizes on the leak-before-break case of pressure vessels and piping with multiple cracks
    Xie, L
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1999, 76 (07) : 435 - 439
  • [40] Leak-Before-Break assessment of a welded piping based on 3D finite element method
    Chen, Mingya
    Yu, Weiwei
    Chen, Zhilin
    Qian, Guian
    Lu, Feng
    Xue, Fei
    ANNALS OF NUCLEAR ENERGY, 2017, 105 : 196 - 204