• Proceedings of the Korean Institute of Industrial Safety Conference
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• 1997.11a
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• pp.185-190
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• 1997

1991년 7월, 미국원자력규제위원회(USNRC)에서 발표한 미국 정비규정1은 5년간의 준비 기간을 거쳐 1996년 7월에 모든 미국 원자력발전소 (이하 "원전"이라 칭함)에 적용되기 시 작하였다. 정비규정의 일부 내용을 간추려 보면 다음과 같다. "모든 원전은 산업체 경험을 고려하여 주요 구조물, 계통, 그리고 기기(Structure, System, Component: SSC)에 대한 성능목표(Performance goal)를 수립해야하고 수립된 목표에 대해 SSC의 상태 또는 성능을 감시(monitoring)해야만 한다. SSC의 성능 또는 상태가 목표와 다를 때는 적절한 보완 조치 가 취해져야 한다". (중략)

• 대한방사선방어학회:학술대회논문집
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• 2011.04a
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• pp.182-183
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• 2011

• Structural Engineering and Mechanics
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• v.43 no.4
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• pp.475-502
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• 2012

In this paper, the seismic analysis modeling technologies for sodium-cooled fast reactor (SFR) are presented with detailed descriptions for each structure, system and component (SSC) model. The complicated reactor system of pool type SFR, which is composed of the reactor vessel, internal structures, intermediate heat exchangers, primary pumps, core assemblies, and core support structures, is mathematically described with simple stick models which can represent fundamental frequencies of SSC. To do this, detailed finite element analyses were carried out to identify fundamental beam frequencies with consideration of fluid added mass effects caused by primary sodium coolant contained in the reactor vessel. The calculation of fluid added masses is performed by detailed finite element analyses using FAMD computer program and the results are discussed in terms of the ways to be considered in a seismic modeling. Based on the results of seismic time history analyses for both seismic isolation and non-isolation design, the functional requirements for relative deflections are discussed, and the design floor response spectra are proposed that can be used for subsystem seismic design.

• International conference on construction engineering and project management
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• 2020.12a
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• pp.353-358
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• 2020

Recent efforts to develop a common standard for nuclear power plants (NPPs) with the aim of creating (1) a digital environment for a better understanding of NPPs life-cycle management aspect and (2) engineering data interoperability by using existing standards among different unspecified project participants (e.g., owners/operators, engineers, contractors, equipment suppliers) during plants' life cycle process (EPC, O&M, and decommissioning). In order to meet this goal, there is a need for formulating a standardized high-level physical breakdown structure (PBS) for NPPs project management office (PMO). However, high-level PBS must be comprehensive enough and able to represent the different types of plants and the new trends of technologies in the industry. This has triggered the need for addressing the issues of the recent operational NPPs and future technologies' ramification for evaluating the changes in the NPPs physical components in terms of structure, system, and component (SSC) configuration. In this context, this ongoing study examines the recent conventional NPPs and technological trends in the development of future NPPs facilities. New reactor models regarding the overlap of variant issues of nuclear technology were explored. Finally, issues on PBS for project management are explored by the examination of the configuration of NPPs primary system. The primary systems' configuration of different reactor models is assessed in order to clarify the need for analyzing the new trends in nuclear technology and to formulate a common high-level PBS. Findings and implications are discussed for further studies.