• Journal of the Earthquake Engineering Society of Korea
• /
• v.27 no.1
• /
• pp.69-75
• /
• 2023

In Korea, most nuclear power plants were designed based on the design response spectrum of Regulatory Guide 1.60 of the NRC. However, in the case of earthquakes occurring in the country, the characteristics of seismic motions in Korea and the design response spectrum differed. The seismic motion in Korea had a higher spectral acceleration in the high-frequency range compared to the design response spectrum. The seismic capacity may be reduced when evaluating the seismic performance of the equipment with high-frequency earthquakes compared with what is evaluated by the design response spectrum for the equipment with a high natural frequency. Therefore, EPRI proposed the inelastic energy absorption factor for the equipment anchorage. In this study, the seismic performance of welding anchorage was evaluated by considering domestic seismic characteristics and EPRI's inelastic energy absorption factor. In order to reflect the characteristics of domestic earthquakes, the uniform hazard response spectrum (UHRS) of Uljin was used. Moreover, the seismic performance of the equipment was evaluated with a design response spectrum of R.G.1.60 and a uniform hazard response spectrum (UHRS) as seismic inputs. As a result, it was confirmed that the seismic performance of the weld anchorage could be increased when the inelastic energy absorption factor is used. Also, a comparative analysis was performed on the seismic capacity of the anchorage of equipment by the welding and the extended bolt.

• Journal of the Korean Society of Safety
• /
• v.22 no.4
• /
• pp.7-12
• /
• 2007

In order to evaluate the integrity of Zr-2.5Nb pressure tubes, probabilistic fracture mechanics(PFM) approach was employed. Failure assessment diagram(FAD), plastic collapses, and critical crack lengths(CCL) were used for evaluating the failure probability as failure criteria. The Kr-FAD as failure assessment diagram was used because fracture of pressure tubes occurred in brittle manner due to hydrogen embrittlement of material by deuterium fluence. The probabilistic integrity evaluation observed AECL procedures and used fracture toughness parameters of EPRI and recently announced theory. In conclusion, the probabilistic approach using the Kr-FAD made it possible to determine major failure criterion in the pressure tube integrity evaluation.

• Proceedings of the Earthquake Engineering Society of Korea Conference
• /
• 2000.04a
• /
• pp.97-104
• /
• 2000

Evaluating a Review-Level Ground Motion is a key to efficiently perform Seismic Margin Assessment of nuclear power plants whose purpose is to determine a ground motion level for which a plant has high-confidence-of-a-low-probability of seismic-induced core damage and to identify any weaker-link components. In this study a method to obtain RLGMs is reviewed which is recommended by Electric Power Research Institute and implemented to be applied to Limerick site in eastern and central U. S as a case study. This method provides reasonable and site-specific RLGMs as minimum required plant HCLPF for SMA that meet a target mean seismic core-damage frequency based on seismic hazard results and generic values of uncertainty and randomness parameters of the core-damage fragility curves. In addition high-frequency RLGM is justifiably modified to reflect the increased seismic capacity of high-frequency components and spatial variation and incoherence of input ground motion on a basemat of large structures by establishing a method to obtain high0-frequency reduction factors according to EPRI guidelines.

• The Transactions of the Korean Institute of Electrical Engineers C
• /
• v.48 no.7
• /
• pp.542-549
• /
• 1999

Corona discharges form at the surface of a transmission line conductor when the electric-field intensity on the conductor surface exceeds the breakdown strength of air. In order to decrease the electric-field intensity on the conductor surface, a new 6 conductor bundle has been studied. This bundle, hybrid conductor bundle, consists of using a larger subconductor at the bottom two conductor positions in the 6-conductor bundles of each phase of the line. The electric field on these two larger subconductors is reduced which in turn reduces the corona noise. It is shown that this is a better solution for decreasing the electric-field intensity than ether the conventional bundle or the asymmetric bundle proposed by EPRI.

• Journal of the Korean Institute of Illuminating and Electrical Installation Engineers
• /
• v.29 no.1
• /
• pp.121-127
• /
• 2015

Recently, LVDC(Low Voltage Direct Current) has been came into the newly spotlight with HVDC(High Voltage Direct Current) and as increasing digital load, DC power supply and high quality of demand is also getting extended. In accordance with the report of EPRI(Electric Power Research Institute), they expect digital load will grow to 50% of whole load in 2020. Subsequently, the use of DC equipment will grow dramatically. Therefore, the careful adoption of LVDC standardization policy is urgently required for the safety of people, prevention of confusion and occupancy of the market.

• Journal of the KSME
• /
• v.31 no.3
• /
• pp.244-250
• /
• 1991

본 글에서는 EPFM을 이용한 구조물의 건전성 평가법을 소개하였다. 이러한 방법을 원자력발 전소 NSSS평가에 적용하면 좀 더 정확한 해석결과를 얻을 수 있으며 불필요한 가동중단이나 보수작업을 피할 수 있다. 한편 ASME XI에서 현재 제정중인 EPFM 관련법규도 소개하였는데, 가까운 장래에 결정될 최종안에는 약간의 내용변화가 있으리라 생각된다. 근래에는 건전성평 가를 위한 컴퓨터 소프트웨어가 많이 개발되어 이용되고 있다. 필자들이 아는 바로는 B & W 사에서 개발한 DPFAD, Structural Integrity Associate 사에서 개발한 PC-CRACK, 그리고 LBB 설계용으로 EPRI에서 개발한 FLET등이 있다. 국내에서는 필자들에 의해 개발된 EPIES가 있 는데 자세한 내용은 관련문헌(10,11)을 참고하기 바란다. 본 글에서 소개한 EPEM 평가법은 원 자력 발전소뿐만 아니라 가동온도가 높고 연성재료가 널리 사용되는 화력 발전설비, 석유, 화 학설비 및 제철설비 등에도 공통적으로 적용될 수 있다.

• Proceedings of the KIEE Conference
• /
• 2011.07a
• /
• pp.1989-1990
• /
• 2011

스마트그리드 즉, 미래 지능형 전력시스템이 추구하는 가장 큰 특징은 표준화 기반의 시스템간 상호운용성과 최신 기술을 이용한 자동화라고 할 수 있겠다. 그러므로 시스템간 상호 운용이 가능한 스마트그리드 시스템의 개발을 위해서는 요구분석부터 전반적인 시스템의 조건을 만족할 수 있도록 고려되어야 한다. 스마트그리드를 위한 전력시스템의 개발에 활용 될 수 있는 방법론으로는 'IEC 62559 IntelliGrid Methodology(IntelliGrid$^{SM}$, 이하 IntelliGrid 방법론)'이 있다. IntelliGrid 방법론은 IEC에 의하여 2007년에 채택된 전력에너지시스템 개발을 위한 방법론(IEC 62559, PAS(Publicly Available Specification))으로, EPRI의 'IntelliGrid 프로그램'의 산출물이다. IntelliGrid 방법론에 기반한 요구분석 방법론을 체계적인 스마트그리드 시스템 개발을 위한 요구분석 방안을 제시한 결과물로 평가할 수 있다. 본 논문에서는 IntelliGrid 방법론의 내용을 분석해 보고, AMI 개발을 위한 요구분석 방법론으로 'IntelliGrid 방법론'을 적용하는 방안 및 절차에 관하여 제시하고자 한다.

• Proceedings of the KIEE Conference
• /
• 2009.07a
• /
• pp.668_669
• /
• 2009

상업운전이 개시된 이래 24년이 경과한 원자력발전소의 480V 저전압분배계통 차단기의 설비특성, 운전 및 정비경험, 현행 정비활동, 경년열화, 성능, 단종 분야를 검토하여 480V 저전압분배계통 차단기에서 제기될 수 있는 현안사항과 이를 해결하기 위한 일련의 수명관리계획을 도출하는 기술성 평가를 수행하였다. 기술성 평가를 통해 제시된 일련의 수명관리계획안에 대하여 비용 및 고장률 데이터를 근거로 EPRI의 LcmVALUE 프로그램을 이용하여 경제성을 분석하고 480V 저전압분배계통차단기의 최적 수명관리계획과 권고사항을 제시하였다.

• IE interfaces
• /
• v.25 no.4
• /
• pp.382-392
• /
• 2012

Reactor protection system to keep nuclear safety and operational economy of plants requires high reliability. Such a high reliability of the system can be achieved through the redundant design of components. However, common cause failures of components reduce the benefits of redundant design. Thus, the common cause failure analysis, to accurately calculate the reliability of the reactor protection system, is carried out using alpha-factor model. Analysis results to 24 operating months are that 1) the system reliability satisfies the reliability goal of EPRI-URD and 2) the common cause failure contributes 90% of the system unreliability. The uncertainty analysis using alpha factor parameters of 0.05 and 0.95 quantile values shows significantly large difference in the system unreliability.

• Transactions of the Korean Society of Pressure Vessels and Piping
• /
• v.16 no.1
• /
• pp.56-64
• /
• 2020

The safety related heat exchangers have been evaluated for their performance during the operation of the nuclear power plant. The evaluation program for the safety related heat exchanger was developed in 2010 and used by KHNP based on EPRI TR-10739 algorithms. The spend fuel pool heat exchanger is one of the safety related heat exchanger in the nuclear power plant and also evaluated for their performance. Recently the performance evaluation for the spend fuel pool heat exchanger was not available because of the decreased heat in the spend fuel pool due to the long term overhaul. This paper analyzes the main cause of evaluation failure in the evaluation process and suggests the criteria for the heat exchanger performance evaluation during the long term overhaul.