• Proceedings of the Korean Nuclear Society Conference
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• 1999.05a
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• pp.424-424
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• 1999

• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.277-283
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• 1997

본 논문에서는 고리원자력발전소용 SSILS(Solid State Interposing Logic System)을 소프트웨어의 건전성을 확보하면서 마이크로프로세서로 설계해 가는 과정을 기술하였다 설계 제작된 시제품은 IEEE Std 344-1975에 따라 내진시험을 하였고 IEEE Std. 323-1983에 따라 환경시험을 필하였다. 그리고 소프트웨어의 건전성은 자체적으로 확인하였다.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.34 no.11
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• pp.1773-1778
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• 2010

To evaluate the structural integrity of the main cooling-water pump of a nuclear power plant under different seismic conditions, the seismic analysis was performed in accordance with IEEE-STD-344 code. The finite element computer program, ANSYS, was used to perform both mode frequency analysis and response spectrum analysis for the pump assembly. The natural frequencies, the mode shapes, and the mode participation factors were obtained from the results of the mode frequency analysis. The stresses resulting from various loadings and their combinations were within the allowable limits specified in the above-mentioned IEEE code. The results of the seismic evaluation fully satisfied the structural acceptance criteria of the IEEE code. Thus, it was proved that the structural integrity of the pump assembly was satisfactory.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.9 no.6
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• pp.1500-1505
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• 2008

To evaluate the structural integrity of the nuclear seismic category IIA bellows seal 2" globe valve under the seismic service conditions the seismic analysis was performed in accordance with ASME, section III, ND-3500, 1989 edition. The finite element computer program, ANSYS, Version 10.0, is used to perform both a mode frequency analysis and an equivalent static seismic analysis of the valve assembly. The mode frequency analysis results show the fundamental natural frequency is greater than 33 Hz and does not exist in seismic range, thus justifying the use of the static analysis. The stresses resulted from various loadings and their combinations are within the allowable limits specified in the above mentioned ASME code. The results of the seismic evaluation fully satisfied the structural acceptance criteria of the ASME code. Accordingly the structural integrity on the globe valve was proved.

• Journal of the Korean Society of Manufacturing Process Engineers
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• v.19 no.4
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• pp.45-51
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• 2020

In this study, a response spectrum analysis of an electric distributing board (EDB) was conducted to investigate seismic integrity in the design stage. For the seismic analysis, the required response spectra of a safe shutdown earthquake with 2% damping (RRS/SSE-2%) specified in GR-63-CORE Zone 4 was used as the ground spectral acceleration input. A finite element method modal analysis of the EDB was also performed to examine the occurrence of resonance within the frequency range of the earthquake response spectrum. Furthermore, static stress caused by deadweight was analyzed. The resultant total maximum stress of the EDB structure was calculated by adding the maximum stresses from both seismic and static loads using the square root of the sum of the squares (SRSS) method. Finally, the structural safety of the EDB was investigated by comparing the resultant total maximum stress with the allowable stress.

• Journal of the KSME
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• v.25 no.4
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• pp.304-311
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• 1985

원자력발전소는 사고시 주변의 인구 및 환경에 미치는 영향의 심각성을 고려하여 가능한 모든 안전조치를 취하여 설계. 건설되도록 하고 있다. 특히 원자로냉각재 계통의 배관이 그러하며 고도의 안전성 및 신뢰성을 확보하기 위하여 지진에 대해서도 구조적인 건전성이 입증되어야 한다. 일반적으로 지진하중에 대한 배관계통의 내진해석에서는 층응답스펙트럼에 의한 모우드 해석 방법이 이용되고 있다. 이 때 내진해석으로 얻어진 응답의 조합에는 신중한 고려가 필요 하다. 즉 배관계통의 특성, 입력지진의 특성, 계산에 고려하는 모우드의 수등을 감안하여 적절한 응답조합이 이루어져야 한다. 본 해설에서는 여러 가지의 응답조합방법과 해석시 고려되는 모 우드의 수를 제한함으로써 발생하는 오차를 보정하기 위한 누락질량효과(missing mass effect)에 대하여 설명하고자 한다. 또 두 가지의 해석모델에 대하여 실제 내진 해석을 수행하여 그 결 과를 비교검토하기로 한다.

• Proceedings of the Korean Nuclear Society Conference
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• 2003.10a
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• pp.475.2-475.2
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• 2003

• Journal of the Korean Institute of Gas
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• v.14 no.6
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• pp.44-50
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• 2010

Vibration responses of a centrifugal pump required dynamic analysis for seismic qualification, were calculated by using spectrum analysis, which is known to be very simple compared with time domain analysis. Modal analysis was performed and the results were utilized in the spectrum analysis. The vibration responses calculated from the spectrum analysis were more conservative than those from the time domain analysis, that is, the former can be used as safer in design process. The pump was qualified for the specified seismic service conditions as specified in IEEE 344-1987. The maximum stresses were less than allowable stress limits. Based on the analysis results, it is concluded that the pump meets all the dynamic requirements of the applicable codes, standards, and technical specification.

• Computational Structural Engineering
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• v.6 no.2
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• pp.79-86
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• 1993

A method to verify seismic qualification of the plant protection system cabinet for a nuclear power plant is presented. A finite element model of the cabinet is developed and the dynamic characteristics are obtained. The results of the modal analysis provide insight into the fundamental dynamic properties of the structure, which correspond to the frequency of the peak values of the input seismic spectrum. It necessitates the design modification of the reference cabinet. Techniques for verifying structural integrity and operability are exemplified by summarizing response spectrum and time history analyses of the structure.

• Proceedings of the Korean Society of Precision Engineering Conference
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• 2012.05a
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• pp.1091-1092
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• 2012