Valves Maintainability Study on Nuclear Power Plant Design Stage

Author(s):  
Xiaohu Yang ◽  
Jiao Deng ◽  
Hong Jiang ◽  
Lifei Yang ◽  
Wen Chen
Author(s):  
Lihua Huang ◽  
Xiang Liu ◽  
Lijuan Wang

An internal flood probabilistic safety assessment (IFPSA) identifies risk-significant flood areas, components and scenarios, and evaluates the risk that a nuclear power plant (NPP) faces under internal flood conditions. This paper draws a comparison between NPPs in operation and those in the design stage with regards to the performance of IFPSA, and the main differences are shown in such tasks as flood area identification, flood source and SSC identification, plant walkdown, flood scenario characterization, flood frequency quantification and flood consequence analysis. Specific cases are presented in order to illustrate the application of IFPSA in NPP design to assess risks, identify potential weak links and provide insights into possible design modifications regarding internal flood protection.


1969 ◽  
Vol 7 (2) ◽  
pp. 181-181
Author(s):  
T. V. Sheehan

Author(s):  
Huie Sha ◽  
Hao Zhang ◽  
Zheng Du ◽  
Yiqiang Xiong ◽  
Yanhua Yang

The objective of COSINE (COre and System INtegrated Engine for design and analysis) project is to develop a software platform which is used for nuclear power plant design and safety analysis. The system code (SYST) is a part of COSINE code. In this paper, the mathematic model of accumulator is established. The model is based on following assumptions: nitrogen above liquid level in accumulator is represented in idea gas equation, water is modeled as an isothermal system. The model for liquid flow include inertia, wall friction, form loss, and gravity effects. Several cases were calculated under different conditions, and the results were compared with RELAP5. It shows that COSINE results agree well with RELAP5.


Author(s):  
Xiaogang He ◽  
Shell Shortes

As a third-generation nuclear power plant design, construction of the Westinghouse AP1000 incorporates the characteristics of modular construction and the “Open-Top” lifting method, which results in many kinds of lifting operations, whose potential failure creates increased risk to key equipment and construction personnel. Lifting by its very nature is high risk. Based on traditional safety management practices utilized at the project, lift operation characteristics were analyzed, and procedures and processes developed to manage the risk. These developed aspects included: lifting operation procedures; a construction scheme review/approval process; work planning/risk mitigation; equipment inspections; personnel certification requirements; training; crew management; special inspections; lessons learned utilization; discipline management; emergency management; and safety culture development. The authors believe that the safety management approaches discussed in this paper can provide guidance in conducting safe lift operations in other nuclear power plant projects.


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