• Journal of the Korean Society for Nondestructive Testing
• /
• v.36 no.4
• /
• pp.295-299
• /
• 2016

Residual foreign objects at the secondary side (top of the tubesheet and tube support plates) of a steam generator are likely to cause a leak by causing wear in the tube. The extent of wear is significantly affected by the material, shape, and size of the foreign object, and the corrosion properties of the tube. The presence of foreign objects at the top of the tubesheet and tube support plates has been identified using remote visual inspection methods such as the foreign object search and retrieval and eddy current test (ECT). The detection of the residual foreign object at the secondary side of a steam generator has limitations that depend on the material properties and the condition of contact with the tube. In this study, which is vertical and horizontal from the upper tubesheet, the corresponding bobbin ECT signals were collected and analyzed to measure its ability to detect foreign objects.

• Transactions of the Korean Society of Mechanical Engineers A
• /
• v.26 no.1
• /
• pp.179-187
• /
• 2002

Finite element analysis was performed to evaluate the integrity of the tubes in the fixed tubesheet of horizontal type heat exchanger under operating condition. For the finite element analysis of the heat exchanger, tubes and tubesheets were equivalently modeled with concentroidal hexagonal columns and solid plates having equivalent properties for the convenience of finite element modeling, respectively. Load combination of tube pressure and thermal expansion most likely to precipitate possible failure of the tubes was selected and applied to the finite element analysis. The compressive stresses of the tubes were calculated based on displacements of each tube, which were obtained from anile element analysis. Finally, the maximum tube stress was compared with the design criterion of ASME Boiler and Pressure Vessel Code Section VIII.

• Explosives and Blasting
• /
• v.17 no.4
• /
• pp.32-50
• /
• 1999

This study deals with interface charactristics of tube and tubesheet of the nuclear steam generator by the explosive expansion in order to take advantage of optimum expansion ratio, pull-out strength and leakage tightness and improvement of the resisitance on the stress corrosion cracking for low residual stress. The paper also show the relationship between roll, hydraulic and explosive expansion. The results obtain are as follows (1) Because of the explosive bonding is to use the high speed pressure and energy by the explosive, workability is good, bonding region is homogenous (2) Expansion ratio is 2.7%, Pull-out strength 850kg, Leakage strength $500kg/cm^2$. Clearance gap is 10~30mm in case of explosive expansion and interface structure of the tube and tubesheet is optimum condition. (3) As the transition region of the explosive expansion is inactive, the resistance of the stress corrosion cracking is increases 30~40% compare to the roll and hydraulic expansion.

• Proceedings of the KWS Conference
• /
• 1999.05a
• /
• pp.126-129
• /
• 1999

• Proceedings of the Korea Information Processing Society Conference
• /
• 2001.10b
• /
• pp.1229-1232
• /
• 2001

코일에 고주파전압을 걸면 교류자계가 발생하며 이 자게 내의 금속재료에 와전류가 발생하는데 와전류는 재료의 재질, 결함, 이종금속, 형상변화 등에 의해 그 발생상태가 다르기 때문에 검출용 코일에서 얻어진 신호성분을 해석함으로써 재료의 비파괴검사가 가능하다. 원자력발전소에서는 증기발생기와 열교환기를 정기적으로 이 와전류 탐상검사를 수행하고 결함상태를 평가하여 그 결과를 대용량 Media에 저장한다. 본 논문에서는 평가결과 정보를 추출하고 변환 처리하여 RDBMS에 입력 관리하는 과정과 다양한 형태의 열교환기 Tubesheet를 편집하는 기능, 사용자의 검색조건 선택에 따라 데이터베이스를 Query하여 Tubesheet에 Mapping 처리하는 기능, 검사주기 및 기기별로 평가결과를 비교 분석할 수 있는 통계/보고서 기기사양정보 및 검사정보관리 등 제반 Application 시스템 구현 결과를 소개한다.

• Korean Journal of Materials Research
• /
• v.5 no.7
• /
• pp.842-849
• /
• 1995

The effect of cathodic protection by the sacrificial anode attached to condenser waterbox of power plant was investigated using numerical analysis. The condenser is consisted of various materials. So in case of no protection, the serious galvanic corrosion between waterbox and tubesheet was observed. If sacrificial anodes were attached to the wall of waterbox or the area corroded galvanically, the large protection effect was showed. To demonstrate the validity of numerical analysis results, model test was executed. The numerical solution was consistent with the experimental vague well.

• Proceedings of the Korean Nuclear Society Conference
• /
• 2001.05a
• /
• pp.285-285
• /
• 2001

• Proceedings of the Korean Nuclear Society Conference
• /
• 2002.05a
• /
• pp.205-205
• /
• 2002

• Journal of the Korean Society of Safety
• /
• v.20 no.2 s.70
• /
• pp.38-43
• /
• 2005

Several nuclear power plants reported that they often found the combination cracks, which consist of longitudinal and circumferential cracks in the tubes. For the burst pressure of a tube with a single longitudinal or circumferential crack several experimental equations have been proposed in published literatures. But for the combination crack appropriate fracture criterion has not been proposed yet. In this study the burst pressures of a tube with a longitudinal crack or a T-type combination crack consisting of longitudinal and circumferential cracks were obtained experimentally and analytically. Fracture parameters such as crack opening angle (COA) were investigated by using elastic plastic analysis. Also the burst pressure far a T-type combination crack located near a tubesheet was considered to develop a length-based criterion. Because most of the axial, circumferential or combination cracks initiate in roll transition zone near the tubesheet.

• Proceedings of the KSME Conference
• /
• 2000.04a
• /
• pp.25-30
• /
• 2000

Residual stresses induced in U-bending and tube-to-tubesheet joining processes of PWR's steam generator row-1 tube were measured by X-ray method and Hole-Drilling Method(HDM). The stresses resulting from the Internal pressure and the temperature gradient in the steam generator were also estimated theoretically. In U-bent lesions, the residual stresses at extrados were induced with compressive stress(-), and its maximum value reached -319 MPa in axial direction at ${\psi}=0^{\circ}$ in position. Maximum tensile residual stress of 170MPa was found to be at the flank side at Position of${\psi}=90^{\circ}$, i.e., at apex region. In tube-to-tubesheet fouling methods, the residual stresses induced by the explosive joint method were found to be lower than that by the mechanical roll method. The gradient of residual stress along the expanded tube was highest at the. transition region, and the residual stress in circumferential direction was found to be higher than the residual stress in axial direction. Hoop stress due to an internal pressure between primary and secondary side was analyzed to be 76 MPa and thermal stress was 45 MPa.