• 제목/요약/키워드: Nuclear Power Plant Structure

검색결과 319건 처리시간 0.027초

APR1400 원자로 내부구조물 종합진동평가프로그램용 측정센서 검토 (A Review of Measuring Sensors for Reactor Vessel Internals Comprehensive Vibration Assessment Program in Advanced Power Reactor 1400)

  • 고도영;이재곤
    • 한국소음진동공학회논문집
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    • 제21권1호
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    • pp.47-55
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    • 2011
  • Reactor vessel internals comprehensive vibration assessment program(RVI CVAP) is one of the necessary tests to ensure the safety of nuclear power plants. RVI CVAP of U.S. nuclear regulatory commission regulatory guide 1.20(U.S. NRC R.G. 1.20) consists of the analysis, measurement and inspection. One of the core technologies of the measurement program for RVI CVAP is to select suitable sensors because the measurement is conducted during the critical path of the construction period of nuclear power plants. Therefore, we analyzed RVI thermal-hydraulic and structure design data of Palo Verde nuclear power plant(U.S.), Yonggwang nuclear power plant(Korea) and APR1400 and researched measuring sensors used in them; moreover, we investigated sensors used for measurement of RVI CVAP for the last 20 years throughout the world. Based on these results, we selected suitable measuring sensors for RVI CVAP in advanced power reactor 1400(APR1400).

진동대 실험을 통한 전단벽 구조물의 층응답 특성 평가 (In-structure Response Evaluation of Shear Wall Structure via Shaking Table Tests)

  • 정재욱;하정곤;함대기;김민규
    • 한국지진공학회논문집
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    • 제25권3호
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    • pp.129-135
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    • 2021
  • After the manual shutdown of the Wolseong nuclear power plant due to an earthquake in Gyeongju in 2016, anxiety about the earthquake safety of nuclear power plants has become a major social issue. The shear wall structure used as a major structural element in nuclear power plants is widely used as a major structural member because of its high resistance to horizontal loads such as earthquakes. However, due to the complexity of the structure, it is challenging to predict the dynamic characteristics of the structure. In this study, a three-story shear wall structure is fabricated, and the in-structure response characteristics of the shear wall structure are evaluated through shaking table tests. The test is performed using the Gyeongju earthquake that occurred in 2016, and the response characteristics due to the domestic earthquake are evaluated.

Issues of New Technological Trends in Nuclear Power Plant (NPPs) for Standardized Breakdown Structure

  • Gebremichael, Dagem D.;Lee, Yunsub;Jung, Youngsoo
    • 국제학술발표논문집
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    • The 8th International Conference on Construction Engineering and Project Management
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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.

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동해안 울진원전의 온배수 방출이 주변 해조군집에 미치는 영향 (Effects of Heated Effluents on the Intertidal Macroalgal Community near Uljin, the East Coast of Korea)

  • 김영환;안중관;이재일;엄희문
    • ALGAE
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    • 제19권3호
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    • pp.257-270
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    • 2004
  • In order to clarify the structure and seasonal dynamics of warm tolerant benthic marine algal community in Korea, the species composition and biomass of marine algae at the discharge canal of Uljin nuclear power plant on the East Coast of Korea were investigated seasonally from February 1992 to October 2000. 107 species of marine algae were found at the discharge canal during the past nine years. In general, the number of species observed was abundant in spring or summer and less in autumn or winter. 27 species (4 blue-green, 5 green, 6 brown and 12 red algae) of marine algae occurred more than 1/ 6 frequency and thus can be categorized as warm tolerant species. Among these, one brown (Dictyota dichotoma) and four red algae (Gelidium amansii, Anphiroa ephedraea, Hydrolithon sargassi, Marginisporum crassissimum) are recorded as warm tolerant marine algae for the first time in Korea. Padina arborescens, Anphiroa zonata and Corallina pilulifera were common species found more than 75% frequency. Seasonal fluctuations of mean biomass were 0-1,330 g dry wt m^(-2) and dominant species in biomass were Corallina pilulifera (contribution to a total biomass proportion 34%), Anphiroa zonata (23%), Padina arborescens (18%) and Sargassum micracanthum (11%). The red algae appeared as predominant algal group at the discharge canal of Uljin nuclear power plant in the qualitative and quantitative aspects. The green algae such as Enterornorpha compressa appeared rather frequently at the discharge canal, but the biomass proportion was very low, in contrast to Kori nuclear power plant where there was definite green algal dominance. Differences in algal communities developed at the discharge canals of Uljin and Kori nuclear power plant on the East Coast of Korea, particularly biomass proportions of green algae, can probably be related to local environmental factors such as water velocity through the canal and natural seawater temperatures.

Development of reutilization system for Nuclear Power Plant Component using Object-Oriented Systems Engineering Method

  • Yeo, Tae Ho;Kim, Tae Ryong;Kim, Chang Lak
    • 시스템엔지니어링학술지
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    • 제12권2호
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    • pp.69-80
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    • 2016
  • The purpose of this study is to establish a component reutilization system in Nuclear Power Plant (NPP) by Object-Oriented Systems Engineering Method (OOSEM). Unified Modeling Language (UML) is mainly used for OOSEM. Operational Concept (OpsCon), Use cases, Structure Diagrams, and Behavior Diagrams are developed to analyze stakeholders needs, system requirements, logical architecture, and physical architecture. Based on the current decommissioning and purchasing system of the component, some activities from their systems were excepted and additional new activities were developed for a component reutilization system.

시스템 다이나믹스를 활용한 원전 조직 및 인적인자 평가 (The System Dynamics Model for Assessment of Organizational and Human Factor in Nuclear Power Plant)

  • 안남성;곽상만;유재국
    • 한국시스템다이내믹스학회:학술대회논문집
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    • 한국시스템다이내믹스학회 2002년도 춘계학술대회발표논문집
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    • pp.19-40
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    • 2002
  • 경제 활동의 근간이 되는 에너지 공급원으로서의 원자력 발전소는 그 경제적 성과의 중요성뿐만 아니라 안전성을 확보하는 것도 매우 중요하다. <그림 1>에서 볼 수 있듯이 원전의 안전성은 하드웨어(hardware) 개선을 포함한 공학적 성능과 조직 및 인적 관리 요소에 대한 부분이 상호 작용하는 시스템 구조를 갖음에도 불구하고, 원전의 경제성과 안전성을 확보하기 위한 조직 및 인적 관리분야에 대한 연구는 기술분야에 비해 상대적으로 소홀히 취급된 경향이 있다.(중략)

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CANDU형 원자로 격납건물의 극한내압능력 평가에 관한 연구 (A Study on Evaluation of Ultimate Internal Pressure Capacity of CANDU-type Nuclear Containment Buildings)

  • 김선훈
    • 한국전산구조공학회논문집
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    • 제24권3호
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    • pp.343-351
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    • 2011
  • 원자로 격납건물은 원자력발전소에서 발생가능한 모든 비상사태에 대한 최후의 방벽 역할을 하고 있다. 따라서 사고발생시 원자로 격납건물의 극한능력을 판단하는 것은 매우 중요하다. 대표적인 고려사항 가운데 하나인 LOCA사고 발생시 CANDU형 원자로 격납건물의 극한능력을 파악하기 위해서는 구조적 안전성 평가를 위한 구조해석이 필요하다. CANDU형 원자로 격납건물은 돔과 원통형벽체로 구성된 프리스트레스 콘크리트 쉘 구조물로서 부착식 텐돈을 사용하고 있다. 본 논문에서는 극한내압능력의 평가를 위하여 3차원 구조해석시스템을 사용한 프리스트레스 콘크리트 격납건물의 비선형해석을 수행하였다.

원전 구조물의 고강도 철근 설계기준 적용을 위한 휨부재 평가 실험 (Performance Evaluation Test of the flexural members of High-Strength Reinforcing Bars for Nuclear Power Plant Structure)

  • 임상준;김석철;이한우
    • 한국건축시공학회:학술대회논문집
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    • 한국건축시공학회 2012년도 추계 학술논문 발표대회
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    • pp.203-204
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    • 2012
  • One of the advantages using High-Strength steel reinforcement in construction is the economic effect due to the decreasing of its quantity. Also, another good effect is the increases of workability by reason of reducing the congestion. This study explain plan of experiment after analysing of ACI 318, 349, 359 to develop 550MPa re-bar design criteria applicable to flexural members of nuclear power plants.

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면진 유체 저장 탱크의 지진취약도 분석 (Seismic Fragility Analysis of Base Isolated Liquid Storage Tank)

  • 안성문;최인길;전영선
    • 한국지진공학회:학술대회논문집
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    • 한국지진공학회 2005년도 학술발표회 논문집
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    • pp.453-460
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    • 2005
  • In this study, the seismic fragility analysis of a base isolated condensate storage tank installed in the nuclear power plant. The condensate storage tank is safety related structure in a nuclear power plant. The failure of this tank affect significantly to the core damage frequency of the nuclear power plants. The seismic analysis of the liquid storage tank was performed by the simple calculation method and the dynamic time storage analysis method. The convective and impulsive fluid mass is modeled as added masses proposed by several researchers. To evaluate the effectiveness of the isolation system, the comparison of HCLPF and core damage frequencies in non-isolated and isolated cases are carried out. It can be found from the results that the seismic isolation system increases the seismic capacity of a condensate storage tank and decreases the core damage frequency significantly.

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Collaboration and Confucian Reflexivity in Local Energy Governance: The Case of Seoul's One Less Nuclear Power Plant Initiatives

  • Lee, Youhyun;Bae, Suho
    • Journal of Contemporary Eastern Asia
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    • 제18권1호
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    • pp.153-174
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    • 2019
  • South Korea's energy policy has been historically established through an energy production structure that relies on thermal and nuclear power generation in relation to a centralized 'Hard Energy System'. However, climate change issues are forcing the transition to renewable energy, and it is crucial for local governments to enable this. This study analyses Seoul city's local energy governance, which is known as One Less Nuclear Power Plant Initiative, by applying the collaborative governance framework inspired by Ansell and Gash (2008) and the Reflexivity framework of Confucianism. It is considered that the local energy governance model of Seoul city can be used as a model by other local governments, and it will eventually lead to a decentralized energy system in this era of energy transition.