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Case Study of Reactor Containment Building Construction in Nuclear Power Plant
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作者 Hyomin Song Sangyong Kim +1 位作者 Yooseok Shin Gwang-Hee Kim 《Journal of Building Construction and Planning Research》 2014年第3期173-182,共10页
It is very important to reduce the construction duration of the Reactor Containment Building (RCB) when considering the more than 50 months on average from concrete placement to completion. Through a case study, this ... It is very important to reduce the construction duration of the Reactor Containment Building (RCB) when considering the more than 50 months on average from concrete placement to completion. Through a case study, this study performs a pre-study for the reduction of construction duration in nuclear power plant project based on construction process of the RCB. The actual data of the case study have been collected and analyze the process and the external wall drawings of the RCB with construction practitioners. As a result of that, it is necessary to modularize the external wall form for equipment hatch and to extend the height of one layer of the external wall form to reduce the construction duration of RCB. The results of this study will be utilized to reduce construction duration of the nuclear power plant. 展开更多
关键词 NUCLEAR reactor NUCLEAR Power PLANT reactor containment building FORM WORK
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A Study on the Structural Response of a PSC Inner Containment Dome with Large Openings Due to Prestress Transfer
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作者 Anirudh A. Desai Sekhar K. Chakrabarti 《World Journal of Nuclear Science and Technology》 2014年第2期103-122,共20页
A linear three dimensional finite element (FE) study has been carried out to examine the structural response of a prestressed concrete (PSC) inner containment (IC) dome of reactor building (double containment system) ... A linear three dimensional finite element (FE) study has been carried out to examine the structural response of a prestressed concrete (PSC) inner containment (IC) dome of reactor building (double containment system) of a typical Indian Nuclear Power Plant, having large steam generator (SG) openings with due emphasis on the local behaviour of the steel-concrete interfaces at the SG openings, due to initial prestress transfer. The predominant thrust of the study has been placed on the objective of predicting the possibilities of separation at the steel-concrete interface zones adjacent to the embedded plates (EPs) of the SG openings. Two types of modeling and analysis have been made to study the overall and local behaviour of the structure. Prestressing ducts, passive reinforcements and EPs have been included in the models in certain ways. For the FE analysis, the interface zone has been modeled using interface elements, the properties of which were derived from the results of past experiments conducted on steel plate-concrete inter-face specimens. The FE analysis results have been compared with the results of the past two FE analytical studies on the linear behaviour of the same PSC IC dome. Important observations have been made regarding dome deformation and stresses throughout the structure with special emphasis on the local behaviour of steel-concrete interfaces at and around the SG openings. 展开更多
关键词 PRESTRESSED Concrete INNER containment reactor building Double containment System STEEL-CONCRETE Interface Steam Generator OPENINGS Steel Embedded Plates
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Comparison of Risk Assessment for a Nuclear Power Plant Construction Project Based on Analytic Hierarchy Process and Fuzzy Analytic Hierarchy Process 被引量:6
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作者 Dae-Woong Shin Yoonseok Shin Gwang-Hee Kim 《Journal of Building Construction and Planning Research》 2016年第3期157-171,共15页
Recently, plant construction throughout the world, including nuclear power plant construction, has grown significantly. The scale of Korea’s nuclear power plant construction in particular, has increased gradually sin... Recently, plant construction throughout the world, including nuclear power plant construction, has grown significantly. The scale of Korea’s nuclear power plant construction in particular, has increased gradually since it won a contract for a nuclear power plant construction project in the United Arab Emirates in 2009. However, time and monetary resources have been lost in some nuclear power plant construction sites due to lack of risk management ability. The need to prevent losses at nuclear power plant construction sites has become more urgent because it demands professional skills and large-scale resources. Therefore, in this study, the Analytic Hierarchy Process (AHP) and Fuzzy Analytic Hierarchy Process (FAHP) were applied in order to make comparisons between decision-making methods, to assess the potential risks at nuclear power plant construction sites. To suggest the appropriate choice between two decision-making methods, a survey was carried out. From the results, the importance and the priority of 24 risk factors, classified by process, cost, safety, and quality, were analyzed. The FAHP was identified as a suitable method for risk assessment of nuclear power plant construction, compared with risk assessment using the AHP. These risk factors will be able to serve as baseline data for risk management in nuclear power plant construction projects. 展开更多
关键词 COMPONENT Analytic Hierarchy Process (AHP) Fuzzy Analytic Hierarchy Process (FAHP) Nuclear Power Plant reactor containment building (rcb) Risk Assessment
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基于无线传感器网络的安全壳裂缝实时监测系统 被引量:1
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作者 徐亚明 黎建洲 周建国 《测绘地理信息》 2017年第3期7-9,13,共4页
反应堆安全壳在整体打压试验期间的表面裂缝实时监测对于掌握安全壳的健康状况具有重要意义。针对现有监测手段存在的不足,利用无线传感器网络技术设计实现了反应堆安全壳表面裂缝实时监测系统。通过在某反应堆安全壳穹顶上进行的一系... 反应堆安全壳在整体打压试验期间的表面裂缝实时监测对于掌握安全壳的健康状况具有重要意义。针对现有监测手段存在的不足,利用无线传感器网络技术设计实现了反应堆安全壳表面裂缝实时监测系统。通过在某反应堆安全壳穹顶上进行的一系列试验,验证了该系统的稳定性。 展开更多
关键词 反应堆安全壳 无线传感器网络 裂缝实时监测系统
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