CANTIA CODE FOR THE PROBABILISTIC ASSESSMENT OF INSPECTION STRATEGIES FOR STEAM GENERATOR TUBES

被引:0
|
作者
Revankar, Shripad T. [1 ]
Wolf, Brian [1 ]
Riznic, Jovica R.
机构
[1] Purdue Univ, Sch Nucl Engn, W Lafayette, IN 47906 USA
来源
IMECE 2008: HEAT TRANSFER, FLUID FLOWS, AND THERMAL SYSTEMS, VOL 10, PTS A-C | 2009年
关键词
CRITICAL 2-PHASE FLOW; CHOKED FLOW; LEAK; MODEL; NONEQUILIBRIUM; CRACKS; SLITS; LIQUID; PIPES; RATES;
D O I
暂无
中图分类号
O414.1 [热力学];
学科分类号
摘要
The Canadian Nuclear Safety Commission (CNSC) recently developed the CANTIA methodology for probabilistic assessment of inspection strategies for steam generator tubes. Assessment of the conditional probabilities Of tube failures, leak rates, and ultimately risk of exceeding licensing dose limits as an approach used to steam generator tube fitness-for-service assessment has been increasingly used in recent years throughout the nuclear power industry. The ANL/CANTIA code predictions were systematically studied to evaluate the code capability to predict the leak rates through the flawed steam generator tubes. In this evaluation the code models on the crack opening area, the probabilistic models and the critical flow rate models were studied and their applicability to available experimental data base was examined.
引用
收藏
页码:1923 / 1932
页数:10
相关论文
共 33 条
  • [1] CRACK GROWTH MODEL FOR THE PROBABILISTIC ASSESSMENT OF INSPECTION STRATEGIES FOR STEAM GENERATOR TUBES
    Wolf, Brian
    Revankar, Shripad T.
    Riznic, Jovica R.
    ICONE 17: PROCEEDINGS OF THE 17TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 1, 2009, : 615 - 621
  • [2] ASSESSMENT OF STEAM GENERATOR TUBE FLAW SIZE AND LEAK RATE MODELS
    Revankar, Shripad T.
    Riznic, Jovica R.
    NUCLEAR TECHNOLOGY, 2009, 167 (01) : 157 - 168
  • [3] A new serpentine array eddy current probe for steam generator tubes inspection
    Zhao, Lei
    Hu, Minghui
    SENSORS AND ACTUATORS A-PHYSICAL, 2024, 377
  • [4] Rotating field eddy current probe with bobbin pickup coil for steam generator tubes inspection
    Xin, Junjun
    Lei, Naiguang
    Udpa, Lalita
    Udpa, Satish S.
    NDT & E INTERNATIONAL, 2013, 54 : 45 - 55
  • [5] Development of ultrasonic guided wave inspection methodology for steam generator tubes of prototype fast breeder reactor
    Narayanan, M. M.
    Kumar, Anish
    Thirunavukkarasu, S.
    Mukhopadhyay, C. K.
    ULTRASONICS, 2019, 93 : 112 - 121
  • [6] Development of in -bore magnetostrictive transducer for ultrasonic guided wave based -inspection of steam generator tubes of PFBR
    Narayanan, M. M.
    Arjun, V.
    Kumar, Anish
    Mukhopadhyay, C. K.
    ULTRASONICS, 2020, 106
  • [7] 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):
  • [8] Influence of thermal expansion bend and tubesheet geometry on guided wave inspection of steam generator tubes of a fast breeder reactor
    Narayanan, M. M.
    Arjun, V
    Kumar, Anish
    STRUCTURAL HEALTH MONITORING-AN INTERNATIONAL JOURNAL, 2021, 20 (06): : 3288 - 3308
  • [9] Sensitivity study of thermal hydraulics to corrosion of heat exchange tubes in steam generator
    Wang, Weibing
    Cheng, Kun
    Wang, Bo
    Zhang, Meng
    Tian, Ruifeng
    NUCLEAR ENGINEERING AND DESIGN, 2023, 402
  • [10] Limit load analyses of helical coiled steam generator tubes with a volumetric flaw
    Seo, H-B
    Ryu, T-Y
    Kim, Y-J
    Chang, Y-S
    Kim, J-W
    Kim, T-W
    FATIGUE & FRACTURE OF ENGINEERING MATERIALS & STRUCTURES, 2012, 35 (11) : 1022 - 1032