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
  • [21] INSPECTION OPTIMIZATION JUSTIFICATION FOR PWR MAIN STEAM AND FEEDWATER NOZZLES USING PROBABILISTIC FRACTURE MECHANICS
    Lohse, C.
    Shim, D. J.
    Somasundaram, D.
    Grizzi, R.
    Stevens, G. L.
    Cinson, T.
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2019, VOL 1, 2019,
  • [22] Evaluation of ECT reliability for axial ODSCC in steam generator tubes
    Lee, Jae Bong
    Park, Jai Hak
    Kim, Hong Deok
    Chung, Han Sub
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2010, 87 (01) : 46 - 51
  • [23] QUANTITATIVE INTEGRATION OF NDT WITH PROBABILISTIC FRACTURE MECHANICS FOR THE ASSESSMENT OF FRACTURE RISK IN PIPELINES
    Kurz, J. H.
    Cioclov, D.
    Dobmann, G.
    Boller, C.
    REVIEW OF PROGRESS IN QUANTITATIVE NONDESTRUCTIVE EVALUATION, VOLS 29A AND 29B, 2010, 1211 : 1941 - 1948
  • [24] Application of probabilistic mechanical studies to optimization of steam generator tube bundle maintenance
    Flesch, B.
    Pitner, P.
    Procaccia, H.
    Riffard, T.
    Granger, B.
    RFM, Revue Francaise de Mecanique, 1993, (02): : 5 - 15
  • [25] PROBABILISTIC FRACTURE MECHANICS EVALUATION OF A BWR FEEDWATER NOZZLE
    Wong, Kevin K. L.
    Dominguez, Garivalde
    Shim, Do Jun
    Richter, Steven K.
    PROCEEDINGS OF ASME 2021 PRESSURE VESSELS AND PIPING CONFERENCE (PVP2021), VOL 1, 2021,
  • [26] Optimization of operation and maintenance of nuclear power plant by probabilistic fracture mechanics
    Maeda, N
    Nakagawa, S
    Yagawa, G
    Yoshimura, S
    NUCLEAR ENGINEERING AND DESIGN, 2002, 214 (1-2) : 1 - 12
  • [27] Evaluation of the Integrity of Steam Generator Tubes Subjected to Flow Induced Vibrations
    Hassan, Marwan
    Riznic, Jovica
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2014, 136 (05):
  • [28] A PROBABILISTIC APPROACH TO SUPPORT HEALTH MANAGEMENT OF STEAM GENERATOR TUBES USING UNCERTAIN INPUTS FROM IN-SERVICE INSPECTIONS
    Chatterjee, Kaushik
    Modarres, Mohammad
    PROCEEDINGS OF THE 20TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING AND THE ASME 2012 POWER CONFERENCE - 2012, VOL 1, 2012, : 593 - 601
  • [29] Strategies for Treating Weld Residual Stresses in Probabilistic Fracture Mechanics Codes
    Brust, Frederick W.
    Kurth, R. E.
    Shim, D. J.
    Rudland, David
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, PVP 2011, VOL 6, A AND B, 2012, : 585 - 593
  • [30] Probabilistic assessment of excessive leakage through steam generator tubes degraded by secondary side corrosion
    Cizelj, L
    Hauer, I
    Roussel, G
    Cuvelliez, C
    NUCLEAR ENGINEERING AND DESIGN, 1998, 185 (2-3) : 347 - 359