• Title/Summary/Keyword: Power Plant Park

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Phytoestrogen Extraction for Relaxation of Female Menopause Symptoms from Natural Products (천연물로부터 여성갱년기 증상완화를 위한 식물성 에스트로겐의 초음파 추출특성)

  • Lee, Seung Bum;Park, So Yeon;Jeon, Gil Song;Hong, In Kwon
    • Applied Chemistry for Engineering
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    • v.27 no.2
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    • pp.217-220
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    • 2016
  • Phytoestrogens are one of quasi-estrogens which are not generated within the endocrine system, but consumed by intaking phytoestrogenic plants. Phytoestrogens, also called as "dietary estrogens", are various botanic chemical compound groups naturally occurring nonsteroidal plant compounds of spontaneous generation. Due to their structural similarities to estrogone, they may provide desirable health benefits for reducing the menopausal symptoms. In this paper, various phytoestrogens were extracted from sophora root, pomegranate and kudzu by ultrasonic extraction process. In this study, the amount of extracted phytoestrogens at various ultrasonic power strengths and extraction times were compared, which could be used as basic data in the study of biology and chemistry related to natural products.

Analysis of Extreme Flood for Nuclear Power Plant Site (원전부지의 방재대책 수립을 위한 극한홍수해석)

  • Keum, Ho Jun;Park, Jun-Hyeong;Heo, Jun Haeng;Han, Kun Yeun
    • Proceedings of the Korea Water Resources Association Conference
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    • 2016.05a
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    • pp.553-553
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    • 2016
  • 2011년 3월 일본 후쿠시마에서 대지진과 쓰나미로 인하여 대규모의 경제적 피해와 생명에 위협을 준 원전사고가 발생하였다. 이처럼 국가주요시설인 원전부지의 사고위험은 다양한 원인으로 인해 늘 위협받고 있으며, 최근 기후변화로 인하여 단시간의 지역적인 집중호우와 예상치 못한 폭우가 빈번하게 발생하고 있는 상황에서 극한홍수로 인한 사고 또한 중요한 원인으로 인식되고 있다. 하지만 우리나라에서는 원전부지에 대하여 PMP 등의 이상강우 조건 하에서 수공학적 안정도 평가와 국가 주요시설물 부지의 침수해석기법의 개발은 아직까지 전무한 실정이다. 따라서 본 연구에서는 원전부지 내에 영향을 미치는 극한강우를 다양한 기법으로 산정하여 가장 큰 피해를 미치는 극한강우 사상을 도출하였다. 도출한 극한강우를 유역유출분석을 통해 실제 원전부지 내로의 유입 경계조건으로 고려하여 2차원 침수해석을 실시하였다. 2차원 침수해석을 위해 원전부지 내 주요시설물, 도로, 하수관망 및 구조물 등을 반영하여 지형자료를 구축하였으며, 유출분석을 통해 유입되는 극한홍수량 외에 원전부지 내로 내리는 직접 강우도 함께 고려하였다. 그 결과를 통해 원전부지 내 침수심 및 유속 분포 등의 침수정보를 제공할 수 있는 침수위험도를 작성하였다. 본 연구를 통해 원전부지 내의 극한강우 산정 및 그로인한 침수위험도 작성으로 원전부지의 방재대책 수립시 기초자료로써 제공될 수 있을 것으로 판단된다.

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A Study on Implementation of RCM for Railway Vehicle (철도차량의 신뢰성기반 유지보수(RCM) 실시 방안)

  • Park, Byoung-Noh;Joo, Hae-Jin;Lee, Chang-Hwan;Lim, Sung-Soo
    • Proceedings of the KSR Conference
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    • 2008.11b
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    • pp.1487-1493
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    • 2008
  • Railway vehicle is very important to implement the effective maintenance in proper to prevent any failure during operation period. Many railway authorities are making efforts to maintain the railway vehicle through scientific and systematic procedure. To achieve this, Reliability Centered Maintenance(RCM) is partially applied. The efficiency of RCM has proven and its terminology was familiar with nuclear power, military and chemical plant etc. since the commercial aircraft's industries has introduced the maintenance program based on the target of reliability. The application of RCM on railway vehicle can be utilized with systematic analysis method to select the best effective maintenance period and action to prevent the failures by selecting the equipment affecting the its safety and reliability. This paper is presented that the procedure of adequate and effective maintenance for railway vehicle by comparing among the related standards in example IEC60300-3,11, MIL-STD-2173, and technical documents or papers. In accordance with above result, RCM procedure is proposed to apply effectively for maintenance of railway vehicle. That is, (1) Analysis of data and Calculation of criticality per equipment (2) Selection of equipment to analyze (3) Analysis of failure mode and effect (4) Evaluation of maintenance method and period (5) Optimization of maintenance program through renewal of maintenance method and period.

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Transient Critical Heat Flux Under Flow Coastdown in a Vertical Annulus With Non-Uniform Heat Flux Distribution

  • Moon, Sang-Ki;Chun, Se-Young;Park, Ki-Yong;Baek, Won-Pil
    • Nuclear Engineering and Technology
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    • v.34 no.4
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    • pp.382-395
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    • 2002
  • An experimental study on transient critical heat flux (CHF) under flow coastdown has been performed for the water flow in a non-uniformly heated vertical annulus under low flow and a wide range of pressure conditions. The objectives of this study are to systematically investigate the effect of the flow transient on the CHF and to compare the transient CHF with steady-state CHF The transient CHF experiments have been performed for three kinds of flow transient modes based on the coastdown data of a nuclear power plant reactor coolant pump. At the same inlet subcooling, system pressure and heat flux, the effect of the initial mass flux on the critical mass flux can be negligible. However, the effect of the initial mass flux on the time-to- CHF becomes large as the heat flux decreases. The critical mass flux has the largest value for slow flow reduction rate. There is a pressure effect on the ratio of the transient CHF data to steady-state CHF data. Except under low system pressure conditions, the flow transient CHF was revealed to be conservative compared with the steady-state CHF data. Bowling CHF correlation and thermal hydraulic system code MARS show promising results for the prediction of CHF occurrence .

Study on multi-unit level 3 PSA to understand a characteristics of risk in a multi-unit context

  • Oh, Kyemin;Kim, Sung-yeop;Jeon, Hojun;Park, Jeong Seon
    • Nuclear Engineering and Technology
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    • v.52 no.5
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    • pp.975-983
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    • 2020
  • Since the Fukushima Daiichi accident in 2011, concerns for the safety of multi-unit Nuclear Power Plant (NPP) sites have risen. This is because more than 70% of NPP sites are multi-unit sites that have two or more NPP units and a multi-unit accident occurred for the first time. After this accident, Probability Safety Assessment (PSA) has been considered in many countries as one of the tools to quantitatively assess the safety for multi-unit NPP sites. One of the biggest concerns for a multi-unit accident such as Fukushima is that the consequences (health and economic) will be significantly higher than in the case of a single-unit accident. However, many studies on multi-unit PSA have focused on Level 1 & 2 PSA, and there are many challenges in terms of public acceptance due to various speculations without an engineering background. In this study, two kinds of multi-unit Level 3 PSA for multi-unit site have been carried out. The first case was the estimation of multi-unit risk with conservative assumptions to investigate the margin between multi-unit risk and QHO, and the other was to identify the effect of time delays in releases between NPP units on the same site. Through these two kinds of assessments, we aimed at investigating the level of multi-unit risk and understanding the characteristics of risk in a multiunit context.

Cohort-based evacuation time estimation using TSIS-CORSIM

  • Park, Sunghyun;Sohn, Seokwoo;Jae, Moosung
    • Nuclear Engineering and Technology
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    • v.53 no.6
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    • pp.1979-1990
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    • 2021
  • Evacuation Time Estimate (ETE) can provide decision-makers with a likelihood to implement evacuation of a population with radiation exposure risk by a nuclear power plant. Thus, the ETE is essential for developing an emergency response preparedness. However, studies on ETE have not been conducted adequately in Korea to date. In this study, different cohorts were selected based on assumptions. Existing local data were collected to construct a multi-model network by TSIS-CORSIM code. Furthermore, several links were aggregated to make simple calculations, and post-processing was conducted for dealing with the stochastic property of TSIS-CORSIM. The average speed of each cohort was calculated by the link aggregation and post-processing, and the evacuation time was estimated. As a result, the average cohort-based evacuation time was estimated as 2.4-6.8 h, and the average clearance time from ten simulations in 26 km was calculated as 27.3 h. Through this study, uncertainty factors to ETE results, such as classifying cohorts, degree of model complexity, traffic volume outside of the network, were identified. Various studies related to these factors will be needed to improve ETE's methodology and obtain the reliability of ETE results.

Study on Development Method of VR Training Contents for Power Plant Safety Education - Focused on sealed space and welding fire - (발전소 안전교육 가상현실 콘텐츠 개발 방법 연구 - 밀폐공간 및 용접화재를 중심으로 -)

  • Min, Seol-hui;Park, Bong-sung;Kim, Yoo-shik;Lee, Sung-Ki;Lee, Dong-Joon;Kang, Ki-Heon
    • Proceedings of the Korea Contents Association Conference
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    • 2019.05a
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    • pp.367-368
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    • 2019
  • 여러 가지 안전사고 항목 중에 밀폐공간 작업과 관련된 사고는 다른 사고에 비해 사망으로 이어질 가능성이 매우 높으며, 사고 발생 시 2명 이상이 동시에 사망하거나 부상당할 가능성이 높은 사고다. 안전보건공단 자료에 의하면, 사고자 2명 중 1명이 밀폐공간 질식사고자이다. 또한 용접작업은 발전소 작업 현장에서는 보일러 튜브 교체 및 수리 등 다양한 부분에서 많이 사용되고 있다. 특히 발전소는 위험물질을 다량 보유하고 있는 곳으로, 고열, 불티에 의한 화재폭발은 대형 인명사고로 이어질 가능성이 매우 높다. 그러나 밀폐공간 작업 및 용접작업에 대한 안전교육은 직접 체험이 어렵기 때문에 효과적인 교육 방법에 대한 연구가 필요하다. 그러므로 본 연구에서는 가상현실 기술을 적용하여 발전소 작업 현장 인원을 대상으로 안전교육이 가능한 밀폐공간 작업 및 용접작업 시 일어날 수 있는 일을 체험할 수 있도록 한 가상현실 안전교육 콘텐츠를 개발한 내용에 대해 살펴보고자 한다.

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An Optimal Model Prediction for Fruits Diseases with Weather Conditions

  • Ragu, Vasanth;Lee, Myeongbae;Sivamani, Saraswathi;Cho, Yongyun;Park, Jangwoo;Cho, Kyungryong;Cho, Sungeon;Hong, Kijeong;Oh, Soo Lyul;Shin, Changsun
    • Smart Media Journal
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    • v.8 no.1
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    • pp.82-91
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    • 2019
  • This study provides the analysis and prediction of fruits diseases related to weather conditions (temperature, wind speed, solar power, rainfall and humidity) using Linear Model and Poisson Regression. The main goal of the research is to control the method of fruits diseases and also to prevent diseases using less agricultural pesticides. So, it is needed to predict the fruits diseases with weather data. Initially, fruit data is used to detect the fruit diseases. If diseases are found, we move to the next process and verify the condition of the fruits including their size. We identify the growth of fruit and evidence of diseases with Linear Model. Then, Poisson Regression used in this study to fit the model of fruits diseases with weather conditions as an input provides the predicted diseases as an output. Finally, the residuals plot, Q-Q plot and other plots help to validate the fitness of Linear Model and provide correlation between the actual and the predicted diseases as a result of the conducted experiment in this study.

Human and organizational factors for multi-unit probabilistic safety assessment: Identification and characterization for the Korean case

  • Arigi, Awwal Mohammed;Kim, Gangmin;Park, Jooyoung;Kim, Jonghyun
    • Nuclear Engineering and Technology
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    • v.51 no.1
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    • pp.104-115
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    • 2019
  • Since the Fukushima Daiichi accident, there has been an emphasis on the risk resulting from multi-unit accidents. Human reliability analysis (HRA) is one of the important issues in multi-unit probabilistic safety assessment (MUPSA). Hence, there is a need to properly identify all the human and organizational factors relevant to a multi-unit incident scenario in a nuclear power plant (NPP). This study identifies and categorizes the human and organizational factors relevant to a multi-unit incident scenario of NPPs based on a review of relevant literature. These factors are then analyzed to ascertain all possible unit-to-unit interactions that need to be considered in the multi-unit HRA and the pattern of interactions. The human and organizational factors are classified into five categories: organization, work device, task, performance shaping factors, and environmental factors. The identification and classification of these factors will significantly contribute to the development of adequate strategies and guidelines for managing multi-unit accidents. This study is a necessary initial step in developing an effective HRA method for multiple NPP units in a site.

Preliminary Study on Effect of Baseline Correction in Acceleration Excitation Method on Finite Element Elastic-Plastic Time-History Seismic Analysis Results of Nuclear Safety Class I Components (원전 안전 1등급 기기의 유한요소 탄소성 시간이력 지진해석 결과에 미치는 가속도 가진 방법 내 기준선 조정의 영향에 대한 예비연구)

  • Kim, Jong-Sung;Park, Sang-Hyeok
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.14 no.2
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    • pp.69-76
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    • 2018
  • The paper presents preliminary investigation results for the effect of the baseline correction in the acceleration excitation method on finite element seismic analysis results (such as accumulated equivalent plastic strain, equivalent plastic strain considering cyclic plasticity, von Mises effective stress, etc) of nuclear safety Class I components. For investigation, finite element elastic-plastic time-history seismic analysis is performed for a surge line including a pressurizer lower head, a pressurizer surge nozzle, a surge piping, and a hot leg surge nozzle using the Chaboche hardening model. Analysis is performed for various seismic loading methods such as acceleration excitation methods with and without the baseline correction, and a displacement excitation method. Comparing finite element analysis results, the effect of the baseline correction is investigated. As a result of the investigation, it is identified that finite element analysis results using the three methods do not show significant difference.