EDDY-CURRENT EXAMINATION OF ONCE THROUGH STEAM-GENERATOR TUBING

被引：0
|
作者：
ABELL, GE [1 ]
机构：
[1] B&W CONSTRUCT CO,COPLEY,OH
来源：
MATERIALS EVALUATION | 1976年 / 34卷 / 09期
关键词：
D O I：
暂无
中图分类号：
TB3 [工程材料学];
学科分类号：
0805 ; 080502 ;
摘要：
引用
收藏
页码：P13 / P13
页数：1
相关论文
共 50 条
  • [21] EVALUATION OF PWR STEAM-GENERATOR TUBING ALLOYS
    BERGE, P
    DONATI, JR
    NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1978, 17 (04): : 291 - 299
  • [22] INSPECTION AND REPAIR OF STEAM-GENERATOR TUBING WITH A ROBOT
    BOEHM, HH
    FORCH, H
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1985, 50 (NOV): : 608 - 609
  • [23] FINITE-ELEMENT SIMULATION OF SUPPORT PLATE AND TUBE DEFECT EDDY-CURRENT SIGNALS IN STEAM-GENERATOR NDT
    PALANISAMY, R
    LORD, W
    MATERIALS EVALUATION, 1981, 39 (07) : 651 - 655
  • [24] A signal processing method for eddy current testing of steam generator tubing
    Chen, GZ
    Yoshida, Y
    Miya, K
    Yamaguchi, A
    NONLINEAR ELECTROMAGNETIC SYSTEMS, 1996, 10 : 728 - 731
  • [25] Optimized Eddy Current Detection of Small Cracks in Steam Generator Tubing
    Radu C. Popa
    Kenzo Miya
    Masaaki Kurokawa
    Journal of Nondestructive Evaluation, 1997, 16 (3) : 161 - 173
  • [26] 2D Eddy Current imaging for steam generator tubing
    Lemenager, C
    Zorgati, R
    Cloarec, C
    Jardet, P
    Jacquot, H
    ELECTROMAGNETIC NONDESTRUCTIVE EVALUATION (II), 1998, 14 : 251 - 260
  • [27] Optimized eddy current detection of small cracks in steam generator tubing
    Popa, RC
    Miya, K
    Kurokawa, M
    JOURNAL OF NONDESTRUCTIVE EVALUATION, 1997, 16 (03) : 161 - 173
  • [28] EDDY-CURRENT TESTING OF COPPER TUBING
    不详
    METAL PROGRESS, 1974, 106 (05): : 98 - 99
  • [29] Optimized eddy current detection of small cracks in steam generator tubing
    Popa R.C.
    Miya K.
    Kurokawa M.
    Journal of Nondestructive Evaluation, 1997, 16 (3) : 161 - 173
  • [30] QUALIFICATION OF A MODEL FOR ONCE-THROUGH STEAM-GENERATOR LOFW TRANSIENTS
    KERN, RC
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1984, 46 : 823 - 824
12345