• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2013.04a
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• pp.589-595
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• 2013

A reactor vessel internals comprehensive vibration assessment program(RVI CVAP) of an advanced power reactor 1400(APR1400) is being verified on the integrity of RVI for the design life of the plant by performing the non-prototype category-2 type on the US Nuclear Regulatory Commission Guide(NRC RG) 1.20, for which consists of a vibration and stress analysis program, a limited vibration measurement program, an inspection program, and the correlation of these programs. The aim of this paper is to describe the plan for the vibration measurement, test and acceptance criteria portion, and documentation and results of the APR1400 RVI CVAP. We will conduct the limited vibration measurement program of the APR1400 RVI CVAP according to the measurement plan and the vibration measurement testing in this paper.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2012.10a
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• pp.300-305
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• 2012

The vibration and stress analysis program of comprehensive vibration assessment program (CVAP) is to verify theoretically the structural integrity of reactor vessel internals (RVI) and to provide the basis for selecting the locations monitored in measurement and inspection programs. This paper covers the verification of the vibration and stress analysis methodology of APR1400 RVI CVAP. The analysis methodology was developed to use 3-dimensional hydraulic and structural models with ANSYS and CFX. To validate the methodology, the hydraulic loads and structural reponses of OPR1000 were predicted and compared with the calculated and measured data in the OPR1000 RVI CVAP. Since the results predicted with this methodology were close to the measured values considerably, it was confirmed that the analysis methodology was developed properly.

• Bulletin of the Society of Naval Architects of Korea
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• v.31 no.3
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• pp.36-42
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• 1994

고품질 선박 평가의 중요한 척도인 진동허용 기준에 대한 관심이 점차 높아지고 있다. 진동 허 용기준은 선박 계약시 건조사양에 포함될 뿐 아니라 건조후 시운전 결과 평가시나 인도후 아프터 서비스 과정에서도 선주와 건조자간에 자주 거론되는 항목이다. 평가 관점으로서는 .승무원의 거주성 및 작업성 .구조 부재의 피로파괴 발생 가능성 .기계기기 기구들의 성능 보존성 등이 있으며 IOS(국제표준화기구)나 여러 선급 기준들이 사용되고 있다. 그러나 보다 쾌적한 거주구나 작업 구역을 원하는 탑승자들의 욕구가 커짐에 따라 최근 저 진동선을 요구하는 선주 들의 허용기준에 대한 관심 또한 늘어나고 있다. 이에 따라 IOS는 선박진동의 종합평가 기준인 IOS 6954 개정 작업을 진행중에 있으며 일부 선급에서도 자체적으로 보완한 기준들을 제시하고 있다. 반면에 조선소들의 입장에서 보면 그간 진동 예측 방법과 방진설계 기술이 발전된 덕분에 심각한 진동문제는 많이 줄어들었다 하겠으나 90년대 아후 선박의 고속화에 따른 기진력 증가로 인하여 저 진동 선박 건조가 쉽지만은 않은 것이 최근의 상황이다. 따라서 본 고에서는 현재 사용되는 각종 선박진동 허용 기준들을 다시 정리하고 그중 강화될 전망이 있는 거주구 진동 허용기준에 대한 변화 추세를 살펴보고자 한다.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.19 no.1
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• pp.1-5
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• 2023

This paper describes a newly-developed analysis methodology in comprehensive vibration assessment program (CVAP) of reactor internals to develop a valid-prototype for the design of nuclear power plants. The new analysis methodology developed in this study will be confirmed through a scale model testing (SMT). Based on the measurements obtained from dynamic pressure transducers in the SMT, a new non-dimensional equation is developed to apply the forcing functions at reactor internals for the prototype. In addition to the new non-dimensional equation, a computational fluid dynamics(CFD) is used to develop the application of the hydraulic loads at reactor internals for the prototype.

• Transactions of the KSME C: Technology and Education
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• v.5 no.2
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• pp.127-134
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• 2017

The reactor internals shall be secured in safety and structural integrity under various vibrational loading conditions. Thus, U.S. NRC, Regulatory Guide 1.20 requires the evaluation for the reactor internals due to acoustic induced vibration including the response to the reactor coolant pump pressure pulsation. This paper suggests a methodology to develop an analytical model of the core support barrel accounting for the fluid around the structure and to analyze the responses to the pump pulsation loads using acoustic structure interaction analysis. The analysis results were compared with those of US Palo Verde 1 CVAP and showed a good agreement. Thus, it is expected that the suggested methodology could be an efficient way to evaluate the response of the core support barrel to the pump pulsation loads.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2011.04a
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• pp.821-826
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• 2011

A basic concept for selection criteria of measuring places of RVI CVAP is to determine measuring places and sensors based on the results of the hydraulic and structural analysis for RVI CVAP in APR1400. In addition, there is the important selection criteria to determine measuring places for measurement of RVI CVAP ; the first is to choose measuring places according to U.S. NRC R.G. 1.20, the second is to select measuring places by RVI design review, the third is to option on the basis of measurement results of SYSTEM 80, the forth is to decide using review results on a design change of a reactor and the last is to determine using the review on the possibility of installation/removal of sensors and structures for the measurement. We developed selection criteria of measuring places for RVI CVAP in APR1400 and this will be directly applied to the measurement program for RVI CVAP.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2014.04a
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• pp.297-299
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• 2014

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2013.10a
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• pp.399-401
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• 2013

• Transactions of the Korean Society for Noise and Vibration Engineering
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• v.23 no.4
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• pp.308-314
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• 2013

The vibration and stress analysis program of comprehensive vibration assessment program(CVAP) is to theoretically verify the structural integrity of reactor vessel internals(RVI) and to provide the basis for selecting the locations monitored in measurement and inspection programs. This paper covers the applicability of the vibration and stress analysis method of APR1400 RVI CVAP. The analysis method was developed to use 3-dimensional detail hydraulic and structural models with ANSYS and CFX. To assess the method, the hydraulic loads and structural reponses of OPR1000 were predicted and compared with the measured data in the OPR1000 RVI CVAP. The results predicted with this method were close to the measured values considerably. Therefore, the analysis method was developed properly.

• Journal of KSNVE
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• v.8 no.1
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• pp.3-72
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• 1998

자동차에서 발생되는 여러가지 문제점들중에서 가장 고객들에게 민감하게 영향을 미치고 중요한 문제가 차량의 정숙성이다.이러한 정숙성을 대변하는 지표중의 하나가 차량에서 발생하는 진동소음의 수준이다. 차량의 지노ㄷㅇ소음은 이러한 정숙성의 문제뿐아니라 승용차를 개발하는 기술력의 종합적인 평가지표로서도 매우 중요한 분야이다. 따라서 이러한 진동소음 문제를 해결하기 위해서 각 자동차의 기술연구소에서는 많은 노력과 시간을 투자하여 이 분야의 기술력 향상에 매진하고 있는 실정이다. 최근에는 보다 적극적인 진동소음 문제 해결 방법으로서 과거에 사용하던 소극적인 문제 해결 방법으로서 과거에 사용하던 소극적이고 방어적인 방법,- 즉 진동소음 발생 현상을 발견하여 그현상을 치유하는 방법에서 벗어나 진동소음 문제를 일으키는 진동소음원(source)을 찾아 직접 그 원인을 차단 및 치유하는 적극적이고 공격적인 방법을 이용하고있다. 본 글에서는 이러한 진동소음 문제를 차량의 개발 단계에서 해결하기 위한 일련의 과정 및 여러가지 개선기법에 대해서 살펴보고 그를 통한 진동소음 문제 해결방법을 제시하고자 한다.