• Nuclear Engineering and Technology
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• 제43권2호
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• pp.175-186
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• 2011

Previous evaluations of the safety of the Ulchin Nuclear Power Plant in the event of a tsunami have the shortcoming of uncertainty of the tsunami sources. To address this uncertainty, maximum and minimum wave heights at the intake of Ulchin NPP have been estimated through a parametric study, and then assessment of the safety margin for the intake has been carried out. From the simulation results for the Ulchin NPP site, it can be seen that the coefficient of eddy viscosity considerably affects wave height at the inside of the breakwater. In addition, assessment of the safety margin shows that almost all of the intake water pumps have a safety margin over 2 m, and Ulchin NPP site seems to be safe in the event of a tsunami according to this parametric study, although parts of the CWPs rarely have a margin for the minimum wave height.

• 한국안전학회지
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• 제17권2호
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• pp.92-99
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• 2002

Safety-related motor operated valve(MOV) safety significance for Ulchin Unit 3 was categorized. The safety evaluation of MOV of domestic nuclear power plants affects the generic data used for the quantification of MOV common cause failure(CCF) events in Ulchin Units 3&4 PSA. Therefore, in this paper, MGL(multiple greek letter)parameter ${\beta}$, used for the evaluation of MOV CCF probabilities in Ulchin Units 3&4 probabilistic safety assessment(PSA), was re-estimated and the MOV safety significance was categorized. The re-estimation results of MGL parameter show that the value of(is decreased by 30% compared with the current value used in Ulchin Unit 3&4 PSA. The categorization results of MOV safety significance using the changed value of MGL parameter(show that the number of HSSCs(high safety significant components) is decreased by 54.5% compared with those using the current value of it used in Ulchin Units 3&4 PSA.

• 대한전기학회논문지:전력기술부문A
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• 제50권8호
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• pp.351-358
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• 2001

This paper deals with the PSS modeling of Ulchin N/P #1 as well as the generator and excitation system modeling by utilizing the recorded data from AVR step test, which has been performed by entering small voltage signal into the AVR summing point. In addition to it. two recorded results obtained from the AVR step test with PSS sunning and without PSS running have not only been compared each other on the time domain, but also they heve been analyzed with FFT analysis on the frequency domain; thus, the desirable effects of running PSS in Ulchin N/P #1 on power system have been explicitly confirmed. Finally, the derived PSS model parameters lead to good matches between simulation results and recorded data.

• 소음진동
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• 제10권1호
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• pp.129-137
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• 2000

This paper presents the vibration characteristics of reactor internals of Ulchin-1 nuclear power plant, which are identified by using the conventional and the phase separated spectral analysis of the pressure vessel acceleration and ex-core neutron signals. These identified vibration characteristics show excellent agreement with those of Tricastin-1 nuclear power plant that is the prototype of Ulchin-1. And the trend of ex-core neutron signals has been observed during one reactor cycle. These results can be used as basic data for fault diagnosis of reactor internals.

• 한국해안해양공학회지
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• 제14권1호
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• pp.1-7
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• 2002

과거, 울진원전 부지의 지진해일에 대한 안전성 평가는 가상최대 지진규모와 그에 상응하는 단층 파라미터를 이용하여 수행되었으나. 최근 지진공백역 이론에 근거하여, 과거 평가 규모 이상의 지진발생 가능성이 지진학자들에 의하여 제기되고 있다. 본 연구에서는 선형·비선형천수방정식 기반의 유한차분법을 이용하여 지진해일 안전성을 재평가하였다. 먼저, '83년 지진해일을 모의하고 이를 동해안 임원항의 최고 범람 수위와 비교하였다. 다음으로 '83년, '93년 지진해일과 위험 단층으로 분류되고 있는 5개 지진공백역 단층에 대하여 울진원전부지 도수로에서의 수위 상승과 저하를 계산하여, 울진원전이 평가대상 단층으로 의한 지진해일 발생시에도 필요 냉각수의 취수가 가능함을 보였다.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2006년도 추계학술대회논문집
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• pp.111-118
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• 2006

The Emergency Diesel Generator(EDG) is a very important piece of equipment for the safety of a Nuclear Power Plant(NPP). In this study, the operating vibration or three kinds or EDG system was measured. The target EDG systems art Yonggwang 5 unit, Ulchin 2 unit and Ulchin 3 unit. The Yonggwang 5 and Ulchin 3 unit EDG system is the same type but the foundation systems are different. One is an anchor bolt type and the other is a spring and viscous-damper type. The purpose of this measurement is for a verification of the vibration isolation effect according to the foundation system. As a result. it can he said that the spring and viscous damper system of the EDG performed well for the vibration isolation.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2000년도 추계학술대회 논문집 학회본부 A
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• pp.152-155
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• 2000

This paper deals with the PSS modelling of Ulchin N/P Unit #1 by utilizing the recorded data from AVR step test. In addition to it, the recorded results obtained from the AVR step test with PSS running and without PSS running are not only compared each other on the time domain but they are also analyzed with FFT on the frequency domain; the desirable effect of running PSS in Ulchin N/P Unit #1 is examined. Finally, the derived PSS model parameters lead to good matches between simulation results and recorded data.

• 대한안전경영과학회지
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• 제7권4호
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• pp.85-99
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• 2005

The main objective of this paper is to search whether containment vessel's best pressure may increase until how long when loss of coolant accident (LOCA) happened in containment vessel of Ulchin nuclear power plant 1 and 2. Another goal of this research is to find the influential factors that increase containment vessel pressure. Model for this research is Ulchin nuclear power plant 1 with 10 cycles. Data were collected by simulator of Ulchin nuclear power plant 1 and design of experiment was used for data analysis. For the experiment, seven factors that are going to influence in containment vessel pressure were chosen. It was found that fatter which influences in early rise of containment vessel pressure after LOCA is only explosion size. Also, containment vessel's best pressure (3.74 bar.a) was much lower than limit (4.86 bar.a) of FSAR (Final Safety Analysis Report).

• Journal of Radiation Protection and Research
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• 제34권4호
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• pp.190-194
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• 2009

울진원자력발전소 주변의 환경시료 해조류에서 검출된 766 keV 감마선에너지 피크를 여러 연구기관에서 $^{95}Nb$ 핵종에서 방출된 것으로 해석하고 있다. 그러나 원전의 액체폐기물 처리설비의 장치개선으로 $^{95}Nb$ 배출량이 현격히 감소하였음에도 불구하고 지속적으로 환경시료에서 $^{95}Nb$ 핵종이 검출되고 있는 현상에 대해서 보다 더 정밀한 기술적인 검토가 필요하였다. 이에 측정 스펙트럼을 정밀 분석한 결과, 766 keV 감마선에너지 피크와 $^{234}Th-^{234}mPa$ 붕괴 계열의 다른 감마선에너지 피크(63, 92 및 1001 keV)들이 동시에 같이 검출되고 있으며, 이들 4종의 감마선에너지 피크 계수율의 시간에 대한 변화로부터 계산된 반감기가 $^{234}Th-^{234}mPa$ 붕괴 계열의 방사평형시 방사능반감기 24.1 일과 매우 비슷한 값을 나타내었다. 또한 766 keV 와 1001 keV 피크의 상대적인 계수율의 비가 $^{234}mPa$의 감마선방출율의 상대적인 비 0.35와 매우 비슷한 값을 나타내었다. 따라서 이러한 점에서 지금까지 $^{95}Nb$ 핵종에서 방출된 것으로 판단했던 766 keV 감마선에너지 피크는 자연방사성핵종인 $^{234}mPa$ 핵종에서 방출된 것으로 판단된다.

• 한국에너지공학회:학술대회논문집
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• 한국에너지공학회 1999년도 추계 학술발표회 논문집
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• pp.125-130
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• 1999

Corrosion of steam generator tubes is the major issue affecting selection of secondary water chemistry parameters. The objective of secondary side water chemistry control is to minimize corrosion damage and to thereby maximize the reliability and economic performance of the secondary system. To achieve this objective, the water chemistry has to be compatible with all parts of the system including steam generators.(Omitted)