• 제목/요약/키워드: out-diameter stress corrosion cracking

검색결과 5건 처리시간 0.021초

증기발생기 전열관지지판의 축균열 파열억제 효과 분석 (Analysis of Tube Support Plate Reinforcement Effects on Burst Pressure of Steam Generator Tubes with Axial Cracks)

  • 강용석;이국희;김홍덕;박재학
    • 한국안전학회지
    • /
    • 제30권4호
    • /
    • pp.168-173
    • /
    • 2015
  • A steam generator tubing is one of the main pressure boundary of the reactor coolant system in the nuclear power plants. Structural integrity refers to maintaining adequate margins against failure of the tubing. Burst pressure of a tube at tube support plate can be higher than that for a free-span tube because failure behaviors could be interfered from the tube support plate. Alternative repair criteria for out-diameter stress corrosion cracking indications in tubes to the drilled type tube support plate were developed, however, there are very limited information to the eggcrate type tube support plate. This paper discussed reinforcement effect of steam generator tube burst pressure with axial out-diameter stress corrosion cracking within an eggcrate type tube support plate. A series of tube burst tests were performed under the room temperature and it was found out that there is no significant but marginal effects.

원전 증기발생기 관판 상단 화학세정 결과 분석 (Analysis of Chemical Cleaning for the Top-of-Tubesheet of NPP's Steam Generator)

  • 이한철;성기방
    • 한국산학기술학회논문지
    • /
    • 제14권4호
    • /
    • pp.2043-2048
    • /
    • 2013
  • 원자력발전소 OPR-1000 CE형 증기발생기는 전열관 재질이 Alloy-600 HTMA으로 되어 있고, 2차측은 퇴적된 슬러지로 인해 ODSCC가 발생한다. ODSCC는 관판 주변에 집중되고 있고, 슬러지 높이에 따라 영향을 받고 있다. 증기발생기 2차측 부식분위기 저감과 함께 전열관의 응력부식균열의 발생을 억제하기 위하여 부분화학세정을 실시하였다. 슬러지 제거량은 259.2kg이고, 퇴적 슬러지 높이는 0.71인치에서 0.34인치로 낮아졌으며, 부식율은 최대 2.34mils로서 EPRI 권고사항인 10mils 이내로 만족하였다.

A Study on the Chemical Cleaning Process and Its Qualification Test by Eddy Current Testing

  • Shin, Ki Seok;Cheon, Keun Young;Nam, Min Woo;Min, Kyong Mahn
    • 비파괴검사학회지
    • /
    • 제33권6호
    • /
    • pp.511-518
    • /
    • 2013
  • Steam Generator (SG) tube, as a barrier isolating the primary coolant system from the secondary side of nuclear power plants (NPP), must maintain the structural integrity for the public safety and their efficient power generation. So, SG tubes are subject to the periodic examination and the repairs if needed so that any defective tubes are not in service. Recently, corrosion related degradations were detected in the tubes of the domestic OPR-1000 NPP, as a form of axially oriented outer diameter stress corrosion cracking (ODSCC). According to the studies on the factors causing the heat fouling as well as developing corrosion cracking, densely scaled deposits on the secondary side of the SG tubes are mainly known to be problematic causing the adverse impacts against the soundness of the SG tubes [1]. Therefore, the processes of various cleaning methods efficiently to dissolve and remove the deposits have been applied as well as it is imperative to maintain the structural integrity of the tubes after exposing to the cleaning agent. So qualification test (QT) should be carried out to assess the perfection of the chemical cleaning and QT is to apply the processes and to do ECT. In this paper, the chemical cleaning processes to dissolve and remove the scaled deposits are introduced and results of ECT on the artificial crack specimens to determine the effectiveness of those processes are represented.

New emerging surface treatment of GFRP Hybrid bar for stronger durability of concrete structures

  • Park, Cheolwoo;Park, Younghwan;Kim, Seungwon;Ju, Minkwan
    • Smart Structures and Systems
    • /
    • 제17권4호
    • /
    • pp.593-610
    • /
    • 2016
  • In this study, an innovative and smart glass fiber-reinforced polymer (GFRP) hybrid bar was developed for stronger durability of concrete structures. As comparing with the conventional GFRP bar, the smart GFRP Hybrid bar can promise to enhance the modulus of elasticity so that it makes the cracking reduced than the case when the conventional GFRP bar is used. Besides, the GFRP Hybrid bar can effectively resist the corrosion of conventional steel bar by the GFRP outer surface on the steel bar. In order to verify the bond performance of the GFRP hybrid bar for structural reinforcement, uniaxial pull-out test was conducted. The variables were the bar diameter and the number of strands and pitch of the fiber ribs. Tensile tests showed a excellent increase in the modulus of elasticity, 152.1 GPa, as compared to that of the pure GFRP bar (50 GPa). The stress-strain curve was bi-linear, so that the ductile performance could be obtained. For the bond test, the entire GFRP hybrid bar test specimens failed in concrete splitting due to higher shear strength resulting in concrete crushing as a function of bar deformation. Investigation revealed that an increase in the number of strands of fiber ribs enhanced the bond strength, and the pitch guaranteed the bond strength of 19.1 mm diameter hybrid bar with 15.9 mm diameter of core section of deformed steel the ACI 440 1R-15 equation is regarded as more suitable for predicting the bond strength of GFRP hybrid bars, whereas the CSA S806-12 prediction is considered too conservative and is largely influenced by the bar diameter. For further study, various geometrical and material properties such as concrete cover, cross-sectional ratio, and surface treatment should be considered.

증기발생기 세관에 대한 근접도 상태 및 최적 평가기법에 대한 연구 (A Study for the Proximity Condition and Optimum Analysis Technique for the SG Tubes)

  • 신기석;문균영;이영호
    • 한국압력기기공학회 논문집
    • /
    • 제4권2호
    • /
    • pp.34-39
    • /
    • 2008
  • Steam Generator(SG) tubes are classified as one of the key components in nuclear power plants, and they should be periodically examined by the intensified management program for the assurance and diagnosis of their structural integrity. In this study, we use the optimum analysis technique to draw the detection and categorization of bowing(BOW) signals; abnormal tube-to-tube proximity in the SG upper bundle free span area. The locations in which BOW signals are detected likely have latent degradation of ODSCC(Outer Diameter Stress Corrosion Cracking). For the sake of timely and correct detection of BOW signals and diagnosis of ODSCC, we carried out the experimental demonstrations using a reduced mock-up. And we validated the MRPC(Motorized Rotating Pancake Coil) analysis technique is better than the bobbin. Hence, it comes to conclusion that the optimum analysis technique can be a good alternative for the reliable SG tube examination.

  • PDF