• 제목/요약/키워드: Nuclear Power Plants

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원자력발전소 직류 전력계통의 충전기 신뢰도 향상방안 연구 (A Study on Battery Charger Reliability Improvement of Nuclear Power Plants DC Distribution System)

  • 임혁순;김두현
    • 한국안전학회지
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    • 제25권2호
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    • pp.24-28
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    • 2010
  • The nuclear power Plant onsite AC electrical power sources are required to supply power to the engineering safety facility buses if the offsite power source is lost. Typically, Diesel Generators are used as the onsite power source. The 125 VAC buses are part of the onsite Class 1E AC and DC electrical power distribution system. The DC power distribution system ensure the availability of DC electrical power for system required to shutdown the reactor and maintain it in a safety condition after an anticipated operational occurrence or a postulated Design Base Accident. Recently, onsite DC power supply system trip occurs the loss of system function. To obtain the performance such as reliability and availability, we analyzed the cause of battery charger trip and described the improvement of DC power supply system reliability. Finally, we provide reliability performance criteria of charger in order to ensure the probabilistic goals for the safety of the nuclear power plants.

원자력발전소 화재에 대한 관할 지역 소방관의 위험인식: 측정도구의 개발과 타당화 (Risk Perception of the Firefighters Responsible for Nuclear Power Plants: Construct Validity)

  • 최해연;이상규;최종안
    • 한국화재소방학회논문지
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    • 제33권5호
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    • pp.94-102
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    • 2019
  • 원전의 안전관리에서 화재 대응의 중요성이 강조되는 시점에서, 화재 대응 인력의 심리적 상태와 역량을 체계적으로 접근할 필요가 있다. 본 연구는 원전 관할 지역 소방관들의 위험인식 구성개념을 규명하고, 이를 측정하는 측정도구를 개발 및 타당화 하였다. 원전 관할 소방관을 대상으로 실시된 인터뷰 분석과 문헌연구를 바탕으로 원전 화재에 대한 위험인식의 문항을 개발하였다. 개발된 문항들에 대한 타당화 연구에는 전라남도, 경상북도 및 부산 소재 원전 관할 소방서 및 119안전센터 5곳에서 참가자를 모집하여 총 180명의 소방관들이 참가하였다. 탐색적 요인분석 결과, 원전 화재의 재난적 결과 및 두려움을 반영하는 '두려움', 원전에서의 화재 및 방사능 누출에 대한 대응 절차와 지침의 부족을 반영하는 '매뉴얼', 원전 화재에 대응할 소방 인력 및 안전장치의 부족을 나타내는 '대응자원', 원전 소방활동을 위한 관계 기관과의 공조와 신뢰를 나타내는 '신뢰', 방사능 및 원전 소방 활동에 대한 지식을 의미하는 '지식'의 5개 요인 구조가 추출되었다. 최종 선별된 15개 문항으로 구성된 척도의 신뢰도와 타당도를 확인하였다. 본 연구 결과를 바탕으로 원전 관할 소방관들의 위험인식의 구성적 특성에 대해서 논의하였다.

Analysis of Korea's nuclear R&D priorities based on private Sector's domestic demand using AHP

  • Lee, Yunbaek;Son, Seungwook;Park, Heejun
    • Nuclear Engineering and Technology
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    • 제52권11호
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    • pp.2660-2666
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    • 2020
  • Korea successfully achieved energy independence in the shortest period of time from being the poorest country in terms of energy 50 years ago through steady development of nuclear technology. In the past, the nuclear industry has been driven through government-centered policy development, public institution-based research, and industrial facility and infrastructure construction. Consequently, South Korea became a nuclear energy powerhouse exporting nuclear power plants to the UAE, surpassing the level of domestic technological independence. However, in recent years, the nuclear industry in Korea has experienced a decline in new plant construction since the Fukushima accident in Japan, which caused changes in public perspectives regarding nuclear power plant operation, more stringent safety standards on the operation of nuclear power plants, and a shift in governmental energy policy. These changes are expected to change the domestic nuclear industry ecosystem. Therefore, in this study, we investigate the priority of technology development investment from the perspective of experts in private nuclear power companies, shifting the focus from government-led nuclear R&D policies. To establish a direction in nuclear technology development, a survey was conducted by applying an analytic hierarchy analysis to experts who have worked in nuclear power plants for more than 15 years. The analysis items of focus were the 3 attributes of strategic importance, urgency, and business feasibility of four major fields related to nuclear energy: nuclear safety, decommissioning, radioactive waste management, and strengthening industrial competitiveness.

Antecedents of self-reported safety behaviors among commissioning workers in nuclear power plants: The roles of demographics, personality traits and safety attitudes

  • Tao, Da;Liu, Zhaopeng;Diao, Xiaofeng;Tan, Haibo;Qu, Xingda;Zhang, Tingru
    • Nuclear Engineering and Technology
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    • 제53권5호
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    • pp.1454-1463
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    • 2021
  • Demographics, personality traits and attitudes are related to safety behaviors in varied workplaces, but their roles in nuclear power plants (NPPs) have not been fully understood. This study was conducted to explore the roles of a set of demographic, personality and attitudinal factors on self-reported safety behaviors (including safety participation and human errors) among NPP commissioning workers. Survey data were collected from 157 Chinese commissioning workers. Results showed that age and work experience were significantly associated with human errors, but not with safety participation. Neuroticism and conscientiousness were significantly related to human errors, while neuroticism, conscientiousness and agreeableness were significantly related to safety participation. Attitude towards questioning was observed as an antecedent of safety participation, and functioned as a mediating variable in the relation between conscientiousness and safety behaviors. The findings provide evidence-based implications on the design of diverse interventions and strategies for the promotion of safety behaviors in NPPs.

Smart support system for diagnosing severe accidents in nuclear power plants

  • Yoo, Kwae Hwan;Back, Ju Hyun;Na, Man Gyun;Hur, Seop;Kim, Hyeonmin
    • Nuclear Engineering and Technology
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    • 제50권4호
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    • pp.562-569
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    • 2018
  • Recently, human errors have very rarely occurred during power generation at nuclear power plants. For this reason, many countries are conducting research on smart support systems of nuclear power plants. Smart support systems can help with operator decisions in severe accident occurrences. In this study, a smart support system was developed by integrating accident prediction functions from previous research and enhancing their prediction capability. Through this system, operators can predict accident scenarios, accident locations, and accident information in advance. In addition, it is possible to decide on the integrity of instruments and predict the life of instruments. The data were obtained using Modular Accident Analysis Program code to simulate severe accident scenarios for the Optimized Power Reactor 1000. The prediction of the accident scenario, accident location, and accident information was conducted using artificial intelligence methods.

가압경수로 원자력 발전소의 전범위 복제형 시뮬레이터 개발 (The Development of Full-Scope Replica Type Simulator for PWR Nuclear Power Plants)

  • 이중근
    • 한국시뮬레이션학회논문지
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    • 제6권1호
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    • pp.85-96
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    • 1997
  • Designing and constructing a proper simulator for real power plants requires extensive research in human engineering and computer science and integration of different fields of technologies such as system analysis, operational knowledge for nuclear plant, etc. A full scope replica type simulator for nuclear power plant is developed. The simulator has the same feature and operational functions as one in the main control room (MCR) of a reference power plant. The simulator provides the necessary training to recover or reduce damages from accidents that usually are unpredictable. This paper describes the configurations and characteristics for the simulator that is developed for Younggwang Nuclear Power Plant #3,4 which is the basic model of the Korean Nuclear Power Plant. The paper also describes technical aspects of Auto Code Generator that is used for developing the simulator. The successful development of the simulator will contribute to improve safety in operation of nuclear power plants.

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확률론적 평가를 이용한 원자력발전소 소내전력공급계통 신뢰도 감시 방법 (A Method to Monitor the Reliability of In-house Power Supply Systems in Nuclear Power Plants Based on Probabilistic Assessment)

  • 박진엽;정동욱
    • 전기학회논문지
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    • 제58권3호
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    • pp.444-449
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    • 2009
  • This paper introduces a method to establish performance criteria of the in-house power supply system in nuclear power plants. The performance criteria of the system is presented in terms of the number of function failures and amount of the out-of-service time that can be allowed commensurate with the probabilistic safety assessment results of the nuclear power plants. To obtain the performance criteria such as reliability and availability, the functions of the system were analyzed and probabilistic assessment results were utilized. This method provides quantitative guidelines in selecting and monitoring system functions to determine an adequate level of maintenance quality in order to ensure the probabilistic goals for the safety of the nuclear power plants.

Measuring Nuclear Power Plant Negative Externalities through the Life Satisfaction Approach: The Case of Ulsan City

  • LEE, KYE WOO;YOO, SE JONG
    • KDI Journal of Economic Policy
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    • 제40권1호
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    • pp.67-83
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    • 2018
  • We have hypothesized that nuclear risk is significantly inversely related to the distance from residences to nuclear power plants and that the level of life satisfaction of residents therefore increases with the distance. We empirically explore the relationship between Ulsan citizens' life satisfaction levels and the distance between their residences and the Kori and Wolsong nuclear power plants (NPP) based on the life satisfaction approach (LSA). The dataset we used covers only Ulsan citizens from the biennial Ulsan Statistics on Citizen's Living Condition and Consciousness of 2014 and 2016. Controlling for micro-variables such as education, work satisfaction, gender, marital status, and expenditures, we found a statistically significant relationship between life satisfaction and the distance between the residences and the nuclear power plants. Nuclear negative externalities including (i) health and environmental impact, (ii) radioactive waste disposal, and (iii) the effect of severe accidents can be quantified in terms of LS units and monetary units. We were able to calculate the monetary value of NPP externalities at $277 per kilometer of distance for Kori and $280 per kilometer of distance for Wolsong at constant 2015 prices. These estimates are quite different from the traditional estimates made with the contingent valuation method, whereas they are similar to the findings of LSA studies abroad. Hence, the need to adopt the LSA in South Korea and policy implications are demonstrated.

A Study on Feasibility Evaluation for Prognosis Systems based on an Empirical Model in Nuclear Power Plants

  • Lee, Soo Ill
    • International Journal of Safety
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    • 제11권1호
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    • pp.26-32
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    • 2012
  • This paper introduces a feasibility evaluation method for prognosis systems based on an empirical model in nuclear power plants. By exploiting the dynamical signature characterized by abnormal phenomena, the prognosis technique can be applied to detect the plant abnormal states prior to an unexpected plant trip. Early $operator^{\circ}{\emptyset}s$ awareness can extend available time for operation action; therefore, unexpected plant trip and time-consuming maintenance can be reduced. For the practical application in nuclear power plant, it is important not only to enhance the advantages of prognosis systems, but also to quantify the negative impact in prognosis, e.g., uncertainty. In order to apply these prognosis systems to real nuclear power plants, it is necessary to conduct a feasibility evaluation; the evaluation consists of 4 steps (: the development of an evaluation method, the development of selection criteria for the abnormal state, acquisition and signal processing, and an evaluation experiment). In this paper, we introduce the feasibility evaluation method and propose further study points for applying prognosis systems from KHNP's experiences in testing some prognosis technologies available in the market.

원전사고 평가를 위한 원전 사건유형분석 시스템(ETAS) 개발 (Development of the Event Type Analysis System (ETAS) for the Accident Evaluation in Nuclear Power Plants)

  • 최영환;김영미
    • 한국압력기기공학회 논문집
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    • 제5권2호
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    • pp.35-39
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    • 2009
  • In this study, Event Type Analysis System (ETAS) is developed for the accident evaluation in nuclear power plant. The ETAS system can be used in supporting regulator and/or operator under event situation in nuclear power plants. The ETAS system can categorize the all transient events to 3 categories such as Down-2000, Down-2173, and Slow Fluctuation. We develop the program structure for ETAS system and web-based ETAS system. The ETAS system will be used as sub module of Knowledge-Based Event Evaluation Network (K-EvENT) which is developing for the against the accident in nuclear power plants.

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