• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 학술논문집
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• pp.254-254
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• 2004

Final disposal of radioactive waste generated from Nuclear Power Plant (NPP) requires the detailed information about the characteristics and the quantities of radionuclides in waste package. Most radionuclides are difficult to measure and expensive to assay. Thus it is suggested to the indirect method by which the concentration of the Difficult-to-Measure (DTM) nuclide is estimated using the correlations of concentration-it is called the scaling factor-between Easy-to-Measure (Key) nuclides and DTM nuclides with the measured concentration of the Key nuclide.(omitted)

• 한국압력기기공학회 논문집
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• 제5권1호
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• pp.25-31
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• 2009

Steam Generator(SG) tube is an important component of Nuclear Power Plant(NPP), which comprises of the pressure boundary of primary system. The integrity of SG tube has been confirmed by the eddy current test every outage. In Korea, Bobbin probe and MRPC probe have been generally used for the eddy current test. Meanwhile the usage of Array probe has gradually increased in U.S., Japan and other countries. In this study, we investigated the defect detection capability of the Array probe through its preliminary application to SG tube inspection. The Array probe has the equivalent capability in the defect detection and sizing as the conventional methods. Thus it is desirable that the Array probe is generally applied to SG tube inspection in the domestic NPPs.

• 한국전산구조공학회:학술대회논문집
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• 한국전산구조공학회 2004년도 가을 학술발표회 논문집
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• pp.379-386
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• 2004

The optimal seismic retrofitting of NPP(Nuclear Power Plant) cabinet structures that contained class 1 relays were studies in this paper. During earthquake event, the failure modes of relays are not appeared in form of structural failure, but are appeared in form of contact chatter of relay. Therefore, the retrofitting of cabinet has to be aimed to the reducing of the structural response, such as acceleration. In this study, the optimal characteristic values of dampers were searched by μ-GA (micro-Genetic Algorithm) scheme for several installation patterns. To keep accuracy and efficiency of analysis, the structural models of cabinet were considered as a frame structure. The responses of structure were obtained in form of acceleration response spectra derived from the results of nonlinear time history analysis including damping nonlinearity. The fitness function of the optimum procedure was constructed based on the ratio of maximum spectral value and target GERS (General Equipment Ruggedness Spectra). The results show the good improvements of fitness fur adequate retrofitting pattern. Especially, the improvements of fitness were remarkable when the damping exponents are proper.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2001년도 추계학술대회논문집A
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• pp.246-251
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• 2001

The performance demonstration round robin test was conducted to quantify the capability of ultrasonic inspection for in-service and to address some aspects of reliability for nondestructive evaluation. The fifteen inspection teams who employed procedures that met or exceeded ASME Sec. XI code requirements detected the pinping of nuclear power plant with various cracks to evaluate the capability of detection. With data from PD-RR test, the performance of ultrasonic nondestructive inspection could be assessed using probability of detection and length and depth sizing of cracks.

• 한국전산구조공학회:학술대회논문집
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• 한국전산구조공학회 2003년도 봄 학술발표회 논문집
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• pp.374-381
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• 2003

In this study, the reduction schemes of ICRS(In-Cabinet Response Spectra), the main part of seismic safety qualification of old nuclear power plant(USI A-46 problem), are studied. To obtain accurate dynamic characteristics of cabinet structure, the cabinet structure modeled by frame model and its eigen analysis is performed. The three types of seismic retrofitting scenarios, such as 1) the installation of bracing, 2) installation of damper, 3) installation of tuned mass damper(TMD), are established and evaluated for the decreasing of ICRS. In the cases of 1) ＆ 2), since, the retrofitted structures show larger ICRS than that of original structure, the careful considerations are need in the application of these methods. Though, the case of TMD show the best retrofitting result, the tuning between the real structure and analysis model is estimated the essential step of retrofitting.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2002년도 춘계학술대회논문집
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• pp.1210-1215
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• 2002

The spent fuel handling tool is used to handle the refuel bundle and treated by hoist rope on the bridge crane. The new developed handling tool of NPP(Nuclear Power Plant) should be conformed the structural stability under earthquake condition. In this study, the stress and seismic analysis of the handling tool are performed by finite element method. Using the Floor Response Spectrum(FRS) obtained through the time history analysis, the modal and seismic analysis under Operating Basis Earthquake(OBE) and Safe Shutdown Earthquake(SSE) load conditions are carried out. Total 4 cases of different locations of the trolly and the hook are investigated. With the spring-damper element, the tension analysis of hoist rope is conducted. The stability of handling tool under earthquake load condition is conformed with regulatory guide.

• 한국지진공학회논문집
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• 제8권5호통권39호
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• pp.65-77
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• 2004

본 연구에서는 원전기기의 내진안전성을 향상시키기 위한 진동대 실험을 수행하였다. 원전 격납건물과 유사한 진동수 특성을 가지는 구조물을 제작하여 실험에 사용하였으며 구조물 내부에 설치된 기기를 모사 하기 위하여 면진장치가 설치된 강체블럭을 층바닥에 설치하였다. 주파수 특성이 상이한 3종류의 지진파를 이용하여 진동대 실험을 수행하였다. 면진장치로는 천연고무베어링(NRB)과 고감쇠고무베어링(HDRB)을 사용하여 고무의 감쇠특성에 따른 면진기기의 효율성을 분석하였다. 또한 입력지진동의 주파수 특성에 따라 적절한 면진장치의 기기면진효과를 평가하였다. 실험결과 적절한 면진장치를 사용함으로써 기기의 지진응답을 크게 줄일 수 있으며 지진에 대한 안전성을 향상키킬 수 있는 것으로 나타났다.

• 방사성폐기물학회지
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• 제13권1호
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• pp.45-53
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• 2015

1978년 고리 1호기의 상업 운전을 시작으로 현재 우리나라에서는 총 23기의 원전이 운영 중에 있다. 운영 중인 원전으로부터 방사성폐기물이 계속 발생되고 누적되어 갈 것이다. 또한 원전의 수명 연장과 신규 원전의 추가 건설 이외에도 제염해체 연구시설 등 각종 원자력 시설에서 발생하는 방사성폐기물은 꾸준히 증가하고 있다. 우리나라는 최근 IAEA에서 권고하는 신 분류기준을 적용한 신분류기준에 대해 원자력안전위원회 고시를 개정하였다. 중·저준위폐기물을 IAEA 신 분류기준을 적용하여 세분화한다면, 약 98%를 차지하는 저준위 및 극저준위 방사성폐기물과 규제면제폐기물을 효과적으로 처분 할 수 있게 된다. 본 논문에서는 신 분류기준을 적용한 해외 적용 사례와 처분 방안 현황을 분석하여 국내에 적용 가능한 최적의 합리적인 적용 방안 및 해체 방사성폐기물량을 산정해 보고자 한다.

• 한국건설순환자원학회논문집
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• 제5권1호
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• pp.45-52
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• 2017

이 연구에서는 고로슬래그 다량 치환 콘크리트의 원전 콘크리트 적용을 위하여 기존 원전 콘크리트와의 내구성능 비교 및 분석을 수행하였다. 연구결과에 따르면 고로슬래그를 50% 치환한 콘크리트의 압축강도는 초기강도는 기존 원전 콘크리트보다 낮지만, 우수한 장기강도를 나타내었다. 반면, 기존 원전 콘크리트의 초기강도는 높았지만, 장기강도 발현율이 낮게 나타났다. 내구성능의 평가결과, 고로슬래그를 50% 치환한 콘크리트의 내구성능은 모든 평가항목에서 플라이애시 20% 치환 콘크리트와 비교하여 동등이상의 성능을 나타내었다. 특히. 저강도에서의 고로슬래그 50% 치환한 콘크리트는 염해 저항성과 탄산화 저항성, 동결융해 저항성의 향상효과가 뚜렷하게 나타났다. 반면, 감마선 조사에 따른 콘크리트 압축강도와 화학성분의 변화는 미미하게 나타났다.

• Nuclear Engineering and Technology
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• 제54권1호
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• pp.84-96
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• 2022

In the worst case, a temporary ignition source (also known as transient combustibles) between two electrical panels can damage both panels. Mitigation strategies for electrical panel fires were previously developed using fire modeling and risk analysis. However, since they do not comply with deterministic fire protection requirements, it is necessary to analyze the boundary values at which combustibles may damage targets depending on various factors. In the present study, a sensitivity analysis of input variables related to the damage threshold of two electrical panels was performed for dimensionless geometry using a Fire Dynamics Simulator (FDS). A new methodology using a damage evaluation map was developed to assess the damage of the electrical panel. The input variables were the distance between the electrical panels, the vertical height of the fuel, the size of the fire, the wind speed and the wind direction. The heat flux was determined to increase as the vertical distance between the fuel and the panel decreased, and the largest heat flux was predicted when the vertical separation distance divided by one half flame length was 0.3-0.5. As the distance between the panels increases, the heat flux decreases according to the power law, and damage can be avoided when the distance between the fuel and the panel is twice the length of the panel. When the wind direction is east and south, to avoid damage to the electrical panel the distance must be increased by 1.5 times compared to no wind. The present scale model can be applied to any configuration where combustibles are located between two electrical panels, and can provide useful guidance for the design of redundant electrical panels.