Quantitative evaluation of maintenance strategies for steam generator tubes using probabilistic fracture mechanics

被引:1
|
作者
Sagisaka, M [1 ]
Isobe, Y [1 ]
Yosimura, S [1 ]
Yagawa, G [1 ]
机构
[1] Nucl Fuel Ind Ltd, Tokai, Ibaraki, Japan
来源
关键词
probabilistic fracture mechanics; steam generators; tubes leakage; rupture; sensitivity analysis; ISI; sampling inspection; maintenance criteria; Inconel; 600; PWSCC;
D O I
10.3327/jaesj.42.1325
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
Using probabilistic fracture mechanics (PFM), we performed qualitative evaluations on effectiveness of various maintenance strategies for steam generator (SG) tubes used in pressurized water reactors (PWRs). Here inspection accuracy, inspection interval, sampling inspection and SCC allowance operation were selected as parameters for sensitivity analyses. Although the analyses were mainly conducted for SG tubes made of Inconel 600 mill anneal (MA) material, additional analyses were performed for assumed materials whose resistance to PWSCC was improved. The results demonstrated that failure probabilities were influenced significantly by the crack propagation law in 1600 material. In both 1600 and the assumed materials, the improvement of inspection accuracy would dramatically reduce the failure probabilities. With respect to SCC allowance operation crack, the results showed that it is preferable to improve the inspection accuracy. The probabilistic approach conducted in this study enables to make effective maintenance strategies with being taken account of various maintenance methods.
引用
收藏
页码:1325 / 1333
页数:9
相关论文
共 50 条
  • [31] A new repair criterion for steam generator tubes with axial cracks based on probabilistic integrity assessment
    Kim, Hyun-Su
    Oh, Chang-Kyun
    Chang, Yoon-Suk
    NUCLEAR ENGINEERING AND DESIGN, 2017, 313 : 10 - 19
  • [32] A comparison of the structural integrity of steam generator tubes based on deterministic and probabilistic crack acceptance criteria
    A. S. Francisco
    T. M. W. Ouverney
    L. P. Moreira
    Journal of the Brazilian Society of Mechanical Sciences and Engineering, 2022, 44
  • [33] Application of probabilistic fracture mechanics in evaluation of existing riveted bridges
    Wang, C. S.
    Chen, A. R.
    Chen, W. Z.
    Xu, Y.
    BRIDGE STRUCTURES, 2006, 2 (04) : 223 - 232
  • [34] A comparison of the structural integrity of steam generator tubes based on deterministic and probabilistic crack acceptance criteria
    Francisco, A. S.
    Ouverney, T. M. W.
    Moreira, L. P.
    JOURNAL OF THE BRAZILIAN SOCIETY OF MECHANICAL SCIENCES AND ENGINEERING, 2022, 44 (03)
  • [35] EVALUATION OF CREEP PROPERTIES OF ALLOY 690 STEAM GENERATOR TUBES AT HIGH TEMPERATURE USING TUBE SPECIMEN
    Kim, Jongmin
    Kim, Woogon
    Kim, Minchul
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2019, VOL 6B, 2019,
  • [36] FRACTURE MECHANICS ANALYSIS OF EBR-II STEAM-GENERATOR DUPLEX TUBING
    WU, TS
    CHOPRA, PS
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 22 (NOV16): : 225 - 225
  • [37] Development of steam generator using falling films on heat transfer tubes
    Umezawa, Shuichi
    Watanabe, Kenji
    Amari, Haruo
    Nihon Kikai Gakkai Ronbunshu, B Hen/Transactions of the Japan Society of Mechanical Engineers, Part B, 2009, 75 (751): : 510 - 512
  • [38] DEVELOPMENT OF STEAM GENERATOR USING FALLING FILMS ON HEAT TRANSFER TUBES
    Umezawa, Shuichi
    Amari, Haruo
    Tsujii, Takayuki
    Watanabe, Kenji
    PROCEEDINGS OF THE INTERNATIONAL CONFERENCE ON POWER ENGINEERING 2009 (ICOPE-09), VOL 3, 2009, : 97 - 102
  • [39] Structural integrity assessments of steam generator tubes using the FAD methodology
    Bergant, Marcos A.
    Yawny, Alejandro A.
    Ipina, Juan E. Perez
    NUCLEAR ENGINEERING AND DESIGN, 2015, 295 : 457 - 467
  • [40] Prognostics for integrity of steam generator tubes using the general path model
    Kim, Hyeonmin
    Kim, Jung Taek
    Heo, Gyunyoung
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2018, 50 (01) : 88 - 96