• 한국압력기기공학회 논문집
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• 제15권1호
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• pp.1-7
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• 2019

In this paper, the regulations and technical standards related to qualification of safety grade equipment in nuclear power plants are critically reviewed with the qualification procedure in terms of structures, systems, and equipment in nuclear power plants. These facilities should be designed and constructed to protect from natural conditions or disasters and to perform their safety functions even in case of postulated accidents. Equipment Qualification is to demonstrate that the safety related equipment is designed and constructed to perform their safety functions under normal and accident conditions. It is classified into environmental qualification and seismic qualification.

• 환경영향평가
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• 제4권2호
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• pp.123-130
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• 1995

The equipment composed of many complicated electronic stuffs undergoes diverse stresses caused by mechanical vibrations during its service. Thus, to ensure its proper operation in the field a simulated vibration test has to be carried out in the laboratory with the Vibration Qualification Level, the test specification, which can include the real environment. In this paper we intent to deal with method and procedure for determining the Vibration Qualification Level so as to estimate the vibration-endurance for the equipment precisely.

• 신재생에너지
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• 제16권4호
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• pp.49-64
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• 2020

Photovoltaic and Thermal collector (PV/T) systems are renewable energy devices that can produce electricity and heat energy simultaneously using solar panels and heat exchangers. Since PV/T systems are exposed to the outdoors, their reliability is affected by various environmental factors. This paper presents a reliability test for a PV/T system and evaluates the test results. The reliability assessment entails performance, environment, safety, and life tests. The factor that had the greatest influence on the life of the system was the hydraulic pressure applied to the heat exchanger. A test was conducted by repeatedly applying pressure to the PV/T system, and a reliability analysis was conducted based on the test results. As a result, the shape parameter (β) value of 5.6658 and the B10life 308,577 cycles at the lower 95% confidence interval were obtained.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2007년도 심포지엄 논문집 정보 및 제어부문
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• pp.143-145
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• 2007

The development of excitation control system (ECS) for emergency diesel generator in nuclear power plant is the replacement project of existing control system to resolve the maintenance problems caused by aging and obsolescence, The excitation control system is classified as a safety-related system. To guarantee the performance of developing excitation control system is equal to or higher than that of other systems, establishing the quality assurance scheme, doing software verification and validation activities, and planning equipment qualification. In this paper, we'd like to introduce the equipment qualification of excitation control system.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2000년도 추계학술대회논문집A
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• pp.498-503
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• 2000

A safety-related equipment for use in Nuclear Power Plant should be needed an Equipment Qualification. This paper presents the approach, methods, philosophies, and procedures for qualifying the large squirrel-cage induction electric pump motors for use in ULCHIN 5&6 Nuclear Power Plants. In this paper, the method of qualification is a combination of type test and analysis method, which is composed of Radiation exposure test, Seismic simulation test, Thermal aging analysis for non-metallic materials and Seismic analysis. It is found that the motor performs its safety function with no failure mechanism under postulated service conditions.

• 한국정밀공학회지
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• 제24권6호
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• pp.72-77
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• 2007

A safety-related equipment for the nuclear power plant should be needed an equipment qualification. In this paper, the approach, methods, philosophies, and procedures for qualifying the large squirrel-cage induction electric pump motors for use in ULCHIN 5, 6 Nuclear Power Plants were presented. The method of qualification is a combination of experimental test and analytic method, which is composed of radiation exposure test, seismic simulation test, thermal aging analysis for non-metallic materials, and seismic analysis. The results showed that the motor performed its safety function with no failure mechanism under postulated service conditions.

• 한국건설관리학회:학술대회논문집
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• 한국건설관리학회 2008년도 정기학술발표대회 논문집
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• pp.794-799
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• 2008

건설 가설재 성능검정제도의 전환기에 들어서 주요 가설재들의 성능검정을 평가하고 선진국의 관련 체계와 비교하여, 안전인증제를 통해 새로운 건설공사용 가설재들의 인증제도를 제안하고자 한다. 현재의 성능검정제도는 1992년에 시작되어 2003년에 재 개정되면서, 3년마다 재 검정을 받도록 하고 있다. 그러나 제조능력을 향상시키지 못하고 업체 간 가격경쟁의 심화로 인해 대부분 같은 형태, 기능의 제품만을 양산하고 있는 실정이다. 기존 성능검정제도에서 안전인증제로의 전환은 보다 체계적인 심사방법 및 품질관리 시스템을 포함하고 있으며, 건설 환경 변화에 대응할 수 있는 다양한 요구사항에 맞춘 규격을 제시할 수 있도록 하고 있다. 안전인증제를 통한 건설공사의 가설재는 의무인증대상과 임의인증대상으로 나누어지며, 종전보다 제품의 품질과 관리 시스템을 향상시켜줄 수 있을 것으로 기대된다.

• 산업경영시스템학회지
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• 제25권3호
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• pp.1-8
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• 2002

This paper investigates different QA standards such as KEPIC QAP, KEPIC END 1200, ISO/1EC 17025 etc. and as a result defines QA elements for Nuclear Power Plant equipment qualification(EQ) in Korea. This paper also proposes a practical QA certification system appropriate for an Integrated Organization for EQ which is being planned to be established in Korea. Since the level of the Korean EQ technology is comparatively low, the Korean manufacturers of the Nuclear Power Plant(NPP) equipment have usually used overseas EQ services. The EQ related organizations in Korea are making efforts to construct the integrated EQ system. In connection with this, it is required that the QA elements and QA certification system suitable for EQ in Korea be developed.

• Nuclear Engineering and Technology
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• 제55권8호
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• pp.2905-2918
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• 2023

The valve assembly used in nuclear power plants is important safety-related equipment. In the new standard, the physical attributes are measured using a valve diagnosis test, which is used in the expansion to other non-tested valves using a quantitative test-basis methodology. With a motor-operated actuator, the state of stem's lubrication is related to physical attributes such as the stem factor and the friction coefficient. This study analyzed the numerical transient of fluid and solid lubrication with a squeeze film effect due to the loading rate on the stem and the stem nut using the experimental data. The differential equation that governs the motion mechanism of the stem and stem nut is established and analyzed. The flow rate, the fluid and the solid contact forces are calculated with the friction coefficient. Finally, we found that a change in the friction coefficient results from a change of the shear force in the solid contact mode during the interchange process between the solid contact mode and the fluid contact mode. The qualitative understanding of the squeeze film effect is expanded quantitatively for forces, thread surface distance, velocity, and acceleration, with consideration of the metal solid contact and fluid contact.

• 대한기계학회논문집 C: 기술과 교육
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• 제3권4호
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• pp.257-264
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• 2015

원자력 발전이 중요한 에너지 공급역할을 담당하기 위해서는 안전성을 확보하고, 사용 후 핵연료 문제를 해결하여야 한다. 이와 같은 문제를 해결하기 위한 방안으로 소듐이나 납비스무스 공융합금 등과 같은 액체금속을 냉각재로 이용하는 방안이 연구되고 있다. 본 논문에서는 액체금속 유동모사 실증 설비 개발을 위한 설계변수 검토, 설계 해석, 구조재의 선정 및 설비 개발 결과를 서술하였다. 설비의 개발은 열수력 해석코드의 해석을 통해 수행되었고 충분한 자연순환 유량을 갖는 설비제작 기술을 확보하였다.