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Methodology of seismic-response-correlation-coefficient calculation for seismic probabilistic safety assessment of multi-unit nuclear power plants

  • Eem, Seunghyun;Choi, In-Kil;Yang, Beomjoo;Kwag, Shinyoung
    • Nuclear Engineering and Technology
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    • v.53 no.3
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    • pp.967-973
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    • 2021
  • In 2011, an earthquake and subsequent tsunami hit the Fukushima Daiichi Nuclear Power Plant, causing simultaneous accidents in several reactors. This accident shows us that if there are several reactors on site, the seismic risk to multiple units is important to consider, in addition to that to single units in isolation. When a seismic event occurs, a seismic-failure correlation exists between the nuclear power plant's structures, systems, and components (SSCs) due to their seismic-response and seismic-capacity correlations. Therefore, it is necessary to evaluate the multi-unit seismic risk by considering the SSCs' seismic-failure-correlation effect. In this study, a methodology is proposed to obtain the seismic-response-correlation coefficient between SSCs to calculate the risk to multi-unit facilities. This coefficient is calculated from a probabilistic multi-unit seismic-response analysis. The seismic-response and seismic-failure-correlation coefficients of the emergency diesel generators installed within the units are successfully derived via the proposed method. In addition, the distribution of the seismic-response-correlation coefficient was observed as a function of the distance between SSCs of various dynamic characteristics. It is demonstrated that the proposed methodology can reasonably derive the seismic-response-correlation coefficient between SSCs, which is the input data for multi-unit seismic probabilistic safety assessment.

Mitigation of seismic responses of actual nuclear piping by a newly developed tuned mass damper device

  • Kwag, Shinyoung;Eem, Seunghyun;Kwak, Jinsung;Lee, Hwanho;Oh, Jinho;Koo, Gyeong-Hoi
    • Nuclear Engineering and Technology
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    • v.53 no.8
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    • pp.2728-2745
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    • 2021
  • The purpose of this study is to reduce seismic responses of an actual nuclear piping system using a tuned mass damper (TMD) device. A numerical piping model was developed and validated based on shaking table test results with actual nuclear piping. A TMD for nuclear piping was newly devised in this work. A TMD shape design suitable for nuclear piping systems was conducted, and its operating performance was verified after manufacturing. The response reduction performance of the developed TMD under earthquake loading on actual piping was investigated. Results confirmed that, on average, seismic response reduction rates of 34% in the maximum acceleration response, 41% in the root mean square acceleration response, and 57% in the spectral acceleration response were shown through the TMD application. This developed TMD operated successfully within the seismic response reduction rate of existing TMD optimum design values. Therefore, the developed TMD and dynamic interpretation help improve the nuclear piping's seismic performance.

Improvement on optimal design of dynamic absorber for enhancing seismic performance of nuclear piping using adaptive Kriging method

  • Kwag, Shinyoung;Eem, Seunghyun;Kwak, Jinsung;Lee, Hwanho;Oh, Jinho;Koo, Gyeong-Hoi
    • Nuclear Engineering and Technology
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    • v.54 no.5
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    • pp.1712-1725
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    • 2022
  • For improving the seismic performance of the nuclear power plant (NPP) piping system, attempts have been made to apply a dynamic absorber (DA). However, the current piping DA design method is limited because it cannot provide the globally optimum values for the target design seismic loading. Therefore, this study proposes a seismic time history analysis-based DA optimal design method for piping. To this end, the Kriging approach is introduced to reduce the numerical cost required for seismic time history analyses. The appropriate design of the experiment method is used to increase the efficiency in securing response data. A gradient-based method is used to efficiently deal with the multi-dimensional unconstrained optimization problem of the DA optimal design. As a result, the proposed method showed an excellent response reduction effect in several responses compared to other optimal design methods. The proposed method showed that the average response reduction rate was about 9% less at the maximum acceleration, about 5% less at the maximum value of the response spectrum, about 9% less at the maximum relative displacement, and about 4% less at the maximum combined stress compared to existing optimal design methods. Therefore, the proposed method enables an effective optimal DA design method for mitigating seismic response in NPP piping in the future.

Sensitivity analysis of failure correlation between structures, systems, and components on system risk

  • Seunghyun Eem ;Shinyoung Kwag ;In-Kil Choi ;Daegi Hahm
    • Nuclear Engineering and Technology
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    • v.55 no.3
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    • pp.981-988
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    • 2023
  • A seismic event caused an accident at the Fukushima Nuclear Power Plant, which further resulted in simultaneous accidents at several units. Consequently, this incident has aroused great interest in the safety of nuclear power plants worldwide. A reasonable safety evaluation of such an external event should appropriately consider the correlation between SSCs (structures, systems, and components) and the probability of failure. However, a probabilistic safety assessment in current nuclear industries is performed conservatively, assuming that the failure correlation between SSCs is independent or completely dependent. This is an extreme assumption; a reasonable risk can be calculated, or risk-based decision-making can be conducted only when the appropriate failure correlation between SSCs is considered. Thus, this study analyzed the effect of the failure correlation of SSCs on the safety of the system to realize rational safety assessment and decision-making. Consequently, the impact on the system differs according to the size of the failure probability of the SSCs and the AND and OR conditions.

Data-Driven Digital Twin for Estimating Response of Pipe System Subjected to Seismic Load and Arbitrary Loads (지진하중 및 임의의 하중을 받는 배관 시스템에 대한 응답을 추정하기 위한 데이터 기반 디지털 트윈)

  • Kim, Dongchang;Kim, Gungyu;Kwag, Shinyoung;Eem, Seunghyun
    • Journal of the Earthquake Engineering Society of Korea
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    • v.27 no.6
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    • pp.231-236
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    • 2023
  • The importance of Structural Health Monitoring (SHM) in the industry is increasing due to various loads, such as earthquakes and wind, having a significant impact on the performance of structures and equipment. Estimating responses is crucial for the effective health management of these assets. However, using numerous sensors in facilities and equipment for response estimation causes economic challenges. Additionally, it could require a response from locations where sensors cannot be attached. Digital twin technology has garnered significant attention in the industry to address these challenges. This paper constructs a digital twin system utilizing the Long Short-Term Memory (LSTM) model to estimate responses in a pipe system under simultaneous seismic load and arbitrary loads. The performance of the data-driven digital twin system was verified through a comparative analysis of experimental data, demonstrating that the constructed digital twin system successfully estimated the responses.

A Shape of the Response Spectrum for Evaluation of the Ultimate Seismic Capacity of Structures and Equipment including High-frequency Earthquake Characteristics (구조물 및 기기의 한계성능 평가를 위한 고진동수 지진 특성을 반영한 응답스펙트럼 형상)

  • Eem, Seung-Hyun;Choi, In-Kil
    • Journal of the Earthquake Engineering Society of Korea
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    • v.24 no.1
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    • pp.1-8
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    • 2020
  • In 2016, an earthquake occurred at Gyeongju, Korea. At the Wolsong site, the observed peak ground acceleration was lower than the operating basis earthquake (OBE) level of Wolsong nuclear power plant. However, the measured spectral acceleration value exceeded the spectral acceleration of the operating-basis earthquake (OBE) level in some sections of the response spectrum, resulting in a manual shutdown of the nuclear power plant. Analysis of the response spectra shape of the Gyeongju earthquake motion showed that the high-frequency components are stronger than the response spectra shape used in nuclear power plant design. Therefore, the seismic performance evaluation of structures and equipment of nuclear power plants should be made to reflect the characteristics of site-specific earthquakes. In general, the floor response spectrum shape at the installation site or the generalized response spectrum shape is used for the seismic performance evaluation of structures and equipment. In this study, a generalized response spectrum shape is proposed for seismic performance evaluation of structures and equipment for nuclear power plants. The proposed response spectrum shape reflects the characteristics of earthquake motion in Korea through earthquake hazard analysis, and it can be applied to structures and equipment at various locations.

Hierarchical Subdivision of Light Distribution Model for Realistic Shadow Generation in Augmented Reality (증강현실에서 사실적인 그림자 생성을 위한 조명 분포 모델의 계층적 분할)

  • Kim, Iksu;Eem, Changkyoung;Hong, Hyunki
    • Journal of Broadcast Engineering
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    • v.21 no.1
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    • pp.24-35
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    • 2016
  • By estimating environment light distribution, we can generate realistic shadow images in AR(augmented reality). When we estimate light distribution without sensing equipment, environment light model, geometry of virtual object, and surface reflection property are needed. Previous study using 3D marker builds surrounding light environment with a geodesic dome model and analyzes shadow images. Because this method employs candidate shadow maps in initial scene setup, however, it is difficult to estimate precise light information. This paper presents a novel light estimation method based on hierarchical light distribution model subdivision. By using an overlapping area ratio of the segmented shadow and candidate shadow map, we can make hierarchical subdivision of light geodesic dome.

Morphological differences between functional and skeletal anterior cross-bite patients (기능성 및 골격성 전치부 반대교합 환자의 형태학적 차이점에 관한 연구)

  • Yoo, Eem-Hak;Kim, Tae-Sun
    • The korean journal of orthodontics
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    • v.31 no.4 s.87
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    • pp.439-445
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    • 2001
  • The Purpose of this study was to compare the dento-skeletal characteristics between functional and skeletal anterior cross-bite patients. Twenty-eight functional anterior cross-bite patients and thirty-one skeletal anterior cross-bite patients were selected as a test and a control group. Mean ages of the test and the control group were $9.6{\pm}1.8$ and $9.9{\pm}1.9$, respectively. Lateral cephalograms were taken. Forty-nine cephalometric variables were measured and statistical analysis was performed to find the morphological differences between the groups. Statistically significant differences were found in the cephalometric variables of cranial deflection, maxillary depth, ANB, convexity, NPo-AB, APDI, Mx 1-SN, Mx 1-NA angle, Mx 1-NA, Md 1-NB angle and Md 1-NB. The test group showed more Class III growth potential, more protruded maxilla, lesser maxillo-mandibular difference, more uprighted and retruded maxillary central incisor, more labially tipped and protruded mandibular central incisor.

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Seismic Response Amplification Factors of Nuclear Power Plants for Seismic Performance Evaluation of Structures and Equipment due to High-frequency Earthquakes (구조물 및 기기의 내진성능 평가를 위한 고주파수 지진에 의한 원자력발전소의 지진응답 증폭계수)

  • Eem, Seung-Hyun;Choi, In-Kil;Jeon, Bub-Gyu;Kwag, Shinyoung
    • Journal of the Earthquake Engineering Society of Korea
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    • v.24 no.3
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    • pp.123-128
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    • 2020
  • Analysis of the 2016 Gyeongju earthquake and the 2017 Pohang earthquake showed the characteristics of a typical high-frequency earthquake with many high-frequency components, short time strong motion duration, and large peak ground acceleration relative to the magnitude of the earthquake. Domestic nuclear power plants were designed and evaluated based on NRC's Regulatory Guide 1.60 design response spectrum, which had a great deal of energy in the low-frequency range. Therefore, nuclear power plants should carry out seismic verification and seismic performance evaluation of systems, structures, and components by reflecting the domestic characteristics of earthquakes. In this study, high-frequency amplification factors that can be used for seismic verification and seismic performance evaluation of nuclear power plant systems, structures, and equipment were analyzed. In order to analyze the high-frequency amplification factor, five sets of seismic time history were generated, which were matched with the uniform hazard response spectrum to reflect the characteristics of domestic earthquake motion. The nuclear power plant was subjected to seismic analysis for the construction of the Korean standard nuclear power plant, OPR1000, which is a reactor building, an auxiliary building assembly, a component cooling water heat exchanger building, and an essential service water building. Based on the results of the seismic analysis, a high-frequency amplification factor was derived upon the calculation of the floor response spectrum of the important locations of nuclear power plants. The high-frequency amplification factor can be effectively used for the seismic verification and seismic performance evaluation of electric equipment which are sensitive to high-frequency earthquakes.

THE CEPHALOMETRIC STUDY OF KOREAN MANDIBULAR ANGLE (한국인 성인 하악각에 대한 두부계측 방사선학적 연구)

  • Park, Jung-Ha;Hwang, Kyung-Gyun;Kim, Yong-Jae;Woo, Soon-Seop;Yoo, Eem-Hak;Shim, Kwang-Sup
    • Journal of the Korean Association of Oral and Maxillofacial Surgeons
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    • v.29 no.4
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    • pp.226-231
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    • 2003
  • The contour of mandibular angle is important for facial esthetics in the oriental population, because the wide and square face is thought to have had an unhappy life. A prominent mandibular angle produces a characteristics quardrangle, coase, and muscular appearance. So, uni- or bi-lateral mandibular angle reduction is usually performed. However, there is little guideline for bi-lateral angle reduction. So, this study was to investigate the pattern of Korean mandibular angle for bi-lateral mandibular angle reduction as guideline. This study was included 66 adult men and women over 19 years old who are having the normal mandibular angle. We measured the posterior border, angle, and inferior border of mandible using cephalometric view. The results of study was as followed : 1. The ratio of posterior mandible was 96.6, 97.3% in male, and 103.0, 106.0% in female. 2. The ratio of mandibular angle(R1-Go/R1-R2) was 120.2% in male, and 117.3% in female. 3. The ratio of inferior mandible(D5, 6, 7, E, F, G/D4) was 97.3, 90.9, 79.5, 65.2, 57.8, 46.9% in male, and 98.5, 91.2, 80.5, 67.6, 59.1, 50.2% in female. The results of this study should be useful to decide accurate amount of reduction.