• 한국압력기기공학회 논문집
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• 제6권2호
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• pp.16-19
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• 2010

In this study, the axial ODSCC occurrence of domestic OPR 1000 steam generator tube was caused by the tube weakness and the sludge accumulation in the secondary side of steam generator. Inconel 600 HTMA used as tube material is related to most of tube leakage accidents in the world and also these ODSCCs were detected mainly at the 5th TSP(Tube Support Plate) to the 8th TSP of hot leg side. These elevations(5th TSP to 8th TSP) pave the way for the sludge accumulation. As a result of EC(Eddy Current) Bobbin and RPC data analysis, ODSCCs were occurred at contact points of tube and tube support plate. The more accumulated sludge, the higher occurrence frequency of ODSCC.

• 한국소음진동공학회논문집
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• 제15권9호
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• pp.1009-1015
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• 2005

Fluid-elastic instability and turbulence excitation for an under developing steam generator are investigated numerically. The stability ratio and the amplitude of turbulence excitation are obtained by using the $PIAT^{(R)}$ (program for integrity assessment of steam generator tube) code from the information on the thermal-hydraulic data of the steam generator. The aspect ratio, the ratio between the height of U-tube from the upper most tube support Plate (h) and the width of two vertical portion of U-tube (w), is defined for geometric parameter study. Several aspect ratios with relocation of tube support plates are adopted to study the effects on the mode shapes and characteristics of flow-induced vibration. When the aspect ratio exceeds value of 1, most of the mode shapes at low frequency are generated at the top of U-tube. It makes very high value of the stability ratio and the amplitude of turbulent excitation as well. We can consider that the local mode shape at the upper side of U-tube will develop the wear phenomena between the tube and the anti-nitration bars such as vortical, horizontal, and diagonal strips. It turns out that the aspect ratio reveals very important parameter for the design stage of the steam generator. The appropriate value of the aspect ratio should be specified and applied.

• 대한기계학회논문집
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• 제17권1호
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• pp.200-214
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• 1993

본 연구에서는 Westinghouse Model 51 증기발생기의 U-bend 영역에서 2차측 유체의 횡단유동으로 유발될 수 있는 튜브군의 유체탄성불안정을 예측하기 위한 해석 을 수행하고 그 대표적인 결과들을 제시하였다. 그리고 U-bend 영역에서 AVB에 의한 튜브의 지지상태와 형태 및 최상부 TSP에서 Denting 또는 이물질 고착으로 인하여 변 경된 튜브의 고정지지조건 등이 튜브의 유체탄성불안정 응답에 미치는 영향을 조사하 였다. 유체탄성불안정 해석과정에서 필수적으로 선행되어야 하는 2차측 3차원 2상 유동장 계산은 증기발생기 열수력 해석용인 ATHOS3 코드로써 수행되었으며, U-튜브의 고유진동수와 모우드 형상은 공학해석용 유한요소 프로그램인 ANSYS코드로써 계산되었 다.

• Nuclear Engineering and Technology
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• 제40권7호
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• pp.561-570
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• 2008

When reactivity insertion such as refueling occurs in CANDU reactors, the power and the water levels are tilted in the upper outer zone of the LZCS (Liquid Zone Control System) and fluctuate unstably for a certain period of time (1-5 days). The instability described above is observed in most CANDU reactors in service around the world, but its root cause is unidentified and no solutions to this problem have been established. Therefore, this study attempted to prove experimentally and analytically that the root cause lies in the hold-up of light water on the top of the TSP (Tube Support Plate) due to the mismatch between net volumetric flow rate of light water and helium crossing the narrowed porous TSP installed within the LZCS compartment. Our method was to perform a hydrodynamic simulation of in/outflow of light water and helium. Two solutions for the aforementioned instability of LZCS are suggested. One is to regulate the compartment for both inflowing helium gas and outflowing light water; the other is to enlarge the flow paths of helium and light water within TSP. The former may be applicable to nuclear reactors in service and the latter to those planned for construction.

• 한국압력기기공학회 논문집
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• 제4권2호
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• pp.50-56
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• 2008

The tubes in heat exchanger are typically made of copper alloy, stainless steel, carbon steel, titanium alloy material. Type-439 ferritic stainless steel is ferromagnetic material, and furnish higher heat transfer rates than austenitic stainless steels and higher resistance to corrosion-induced flaws. Ferritic stainless steel can be found in low-pressure(LP) feedwater heaters and moisture separator reheaters(MSRs) in turbine system. LP feedwater heaters generally utilize thin wall Type-439 stainless steel tubing, whereas MSRs typically employ a heavier wall tubing with integral fins. Service-induced damage can occur on the O.D(outside diameter) surface of Type-439 ferritic stainless steel tubing which is employed for MSRs tubing, and the most typical damage mechanism is vibration-induced tube-to-TSP(tube support plate) wear and fatigue cracking. The wear has been reported that occurs mainly on the OD surface. Accordingly, in this study, we have evaluated the flaw sizing capability of magnetic saturation eddy current technique using magnetic saturation probe and flawed specimen.

• 비파괴검사학회지
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• 제28권5호
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• pp.407-415
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• 2008

원전 발전소 터빈계통을 구성하는 열교환기 튜브는 일반적으로 구리합금, 스테인리스강, 탄소강, 티타늄합금 등의 재질로 제작된다. 이들 재질중에서 페라이트계 type-439 스테인리스강은 자성 재질로서 오스테나이트계보다 더 높은 열전달율 가지며, 부식에 의해 유발되는 결함에 대해 더 높은 저항성을 가진다. 페라이트계 스테인리스강은 보통 발전소 열교환기의 저압급수가열기와 습분분리재열기에 사용된다. 저압급수가열기는 일반적으로 두께가 얇은 type-439 스테인리스강을 이용하는 반면에 습분분리재열기는 더 두꺼운 핀튜브를 사용한다. 이와 같이 터빈 습분분리재열기 튜브로 사용되는 type-439 스테인리스강 핀튜브는 터빈계통의 운전으로 인하여 손상이 발생할 수 있다. 손상에 의한 가장 대표적인 결함은 진동에 의해 발생할 수 있는 마모, 피로균열 등이며 마모성 결함은 일반적으로 튜브-튜브지지판에서 발생되는 것으로 보고되고 있다. 본 연구에서는 type-439 스테인리스강 자성체 튜브에 발생할 수 있는 결함을 검출하고 크기를 측정할 수 있는 자기포화 와전류탐상검사 기법의 능력을 평가하였다.