• Journal of Mechanical Science and Technology
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• 제14권2호
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• pp.207-214
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• 2000

Fracture phenomenon has been reported on blades, rotors, connections and rotor discs of LP turbines of nuclear power plants, which is caused by fatigue, stress corrosion and erosion. In this study, as a tool of reliability evaluation, a number of stress and fracture analyses were performed on the defected area under various operating conditions using the finite element method. Possible defects on key-way and rotor disc were assumed to be two-dimensional cracks and centrifugal force, temperature distribution and shrink-fit effect were included as external loads. From stress analysis results, stress intensity factors were obtained and these values can be utilized to evaluate reliability and predict remaining lifetime of the turbine discs.

• Nuclear Engineering and Technology
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• 제45권4호
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• pp.553-564
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• 2013

This study evaluates the local damage of a turbine in an auxiliary building of a nuclear power plant due to an external impact by using the LS-DYNA finite element program. The wall of the auxiliary building is SC structure and the material of the SC wall plate is high manganese steel, which has superior ductility and energy absorbance compared to the ordinary steel used for other SC wall plates. The effects of the material of the wall, collision speed, and angle on the magnitude of the local damage were evaluated by local collision analysis. The analysis revealed that the SC wall made of manganese steel had significantly less damage than the SC wall made of ordinary steel. In conclusion, an SC wall made of manganese steel can have higher effective resistance than an SC wall made of ordinary steel against the local collision of an airplane engine or against a turbine impact.

• Nuclear Engineering and Technology
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• 제52권8호
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• pp.1862-1870
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• 2020

The purpose of this study is to investigate the effect of welding residual stress on operating stress in designing a nuclear turbine welded rotor. A two-dimensional axisymmetric finite element model is employed to calculate the residual stress before and after post weld heat treatment (PWHT), and then the superposition of residual stress after PWHT and operating stress at normal speed and overspeed were discussed. The investigated results show that operating stress can be affected significantly by welding residual stress, and the distribution trend of superposition stress at the weld area is mainly determined by welding residual stress. The superposition of residual stress and operating stress is linear superposition, and the hoop stress distribution of superposition stress is similar with the distribution of residual stress. With the increasing overspeed, the distribution pattern of the hoop superimposed stress remains almost unchanged, while the stress level increases.

• 대한기계학회논문집
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• 제13권3호
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• pp.490-499
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• 1989

본 연구에서의 CO$_{2}$ 프로세스는 1차 루프인 원자로에서 유도되는 나트륨 과 2차 루프인 CO$_{2}$ 가스터빈 사이클로 구성하였고, CO$_{2}$ 임계점 부근에서 압축을 행하였다. 또한 최적의 사이클을 결정하기 위해 h-s 선도와 이에 대한 열역 학적, 칼로리로 유도하였다. 그리고 최적화를 위해 출력을 각각 300,600, 1000MWe로 선택하였고, 터빈 입구압은 150-350bar의 범위로 선택하였으며 이들로부터 열효율에 영향을 주는 각 설계변수의 특성을 연구 분석하였다.

• 한국압력기기공학회 논문집
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• 제6권1호
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• pp.1-8
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• 2010

The existing maintenance program is focused on time-based maintenance to inspect and repair components according to maintenance period, rather than condition-based maintenance or predictive maintenance. The preventive maintenance template of the steam turbine has been developed for optimizing maintenance procedure and improving reliability and availability of the steam turbine of nuclear power plants based on EPRI PM template methodology and EPRI technical reports about preventive maintenance.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2000년도 춘계학술대회논문집
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• pp.664-669
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• 2000

Angular misalignment is one of the important causes for shaft vibration of turbine-generator in 1000MW nuclear power plant. It may cause the plant unexpected shutdown and subsequent accident. The change of dynamic characteristics in journal bearing and rotor due to angular misalignment in high pressure turbine is analyzed. The stiffness/damping coefficients of journal bearing increase as angular misalignment. Subsequently the natural frequency of HP turbine is changed. It was found that the natural frequency may locate near 2 times operating frequency in case of severe misalignment.

• 한국에너지공학회:학술대회논문집
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• 한국에너지공학회 1994년도 춘계학술발표회 초록집
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• pp.130-137
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• 1994

As a part of developing engineering simulator for CANDU 6 nuclear power plants, present paper gives the tentative simulation results of reactor and turbine power transients including reactor-follow-turbine operation. One point kinetics equations are used for neutron dynamics, iodine and xenon loads. To calculate time-dependent high and low pressure turbine powers and grid frequency deviation, simple first order differential equations are used. In addition, control logics (reactor regulating system, demand power routine, and unit power regulator) used in the plant's process computers have been referenced.

• 대한기계학회논문집A
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• 제36권4호
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• pp.373-378
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• 2012

본 논문에서는 공통원인고장을 고려하여 증기터빈 비산확률을 평가하였다. 이 과정에서 저속 및 고속에서 터빈 비산물 발생 경로를 제시하고, 고장수목을 활용하여 비산물 발생빈도를 구하였다. 공통원인고 장을 고려하기 위해서 Alpha Factor 방법론을 사용하였다. 순차 및 비순차 시험에 대해서 각각의 빈도를 비교분석 하였으며, 불확실성을 평가하였다. (1) 고속회전에 의한 연성파괴로 발생하는 터빈비산물 방출빈도는 8.005E-7/year로 평가되었다. (2) 만약, 공통원인고장이 고려되면, 시험방식에 따라 11% 및 33%의 방출빈도 증가를 확인하였다. (3) 사용된 CCF 변수의 불확실성을 고려하면, 터빈방출빈도는 90%의 신뢰도 기준 9.35E-7에서 1.13E-6 사이에 존재함을 알 수 있었다.

• 비파괴검사학회지
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• 제24권4호
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• pp.371-377
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• 2004

원자력 발전소의 터빈에서 운전 연수 증가에 따라 pin finger형 블레이드 루트부에 균열이 발생하는 문제점이 발생되었다. 블레이드 루트부에 대한 비파괴검사는 매 계획 예방 정비기간 동안 수동 초음파 검사를 통하여 수행되어 왔으나, 검사의 신뢰성을 확보하기 위해 해당 설비에 대한 자동 초음파 검사 기술 개발의 필요성이 대두되었으며, 이에 따라 자동 초음파 검사 장비 및 검사 기술을 개발하였다. 개발된 검사 장비의 적용성을 확인하기 위해 계획 예방 정비 기간 중 저압터빈 2, 3단 블레이드 루트부에 대한 자동 초음파 검사를 수행하고, 다양한 형태의 터빈 검사에 확대 적용 가능성을 확인하였다.

• 한국소음진동공학회논문집
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• 제23권10호
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• pp.895-901
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• 2013

Last blades of LP turbine in nuclear power plant are the highly damaged part and suffered from nozzle steam impulses during the turbine operation. Nozzle impulse is known as a common cause of damage or failure in the turbine blade and results from steam flow distortions due to uneven steam flow patterns between the stationary blade vanes. If impulse force was continuously acting on the blade for a long time, crack or wear will occur in weak parts such as root. So, it is important to know variation of nozzle impulse during the blade moving. But there is no way to measure and estimate the magnitude and direction of nozzle impulse. Therefore, this study was performed to know the variation of nozzle impulse force according to the positions of the blade and to obtain blade equivalent force and torque. This results can be used for blade stress estimation.