Application of Combining 3D Model and Survey on Site to Simulate Dome Lifting

2021 ◽  
Author(s):  
Wei-ting He ◽  
Yuan-xia Zhou ◽  
Jie Yang
Keyword(s):  
Power Plant ◽  
Survey Data ◽  
Nuclear Power ◽  
3D Model ◽  
Early Stage ◽  
Design Management ◽  
Plant Design ◽  
Nuclear Power Project ◽  
Power Project ◽  
Elimination Scheme

Abstract Dome lifting is one of the most important milestones for nuclear power project. The lifting operation must be properly planned and carried out in safety manner. The simulation and analysis are usually done before lifting activities to ensure the smooth lifting implementation. By using of 3D model and survey data on site to assist dome lifting, the risks related to lifting activities can be discovered and the risk elimination scheme can be formulated at early stage. Combining with Power Plant Design Management System (PDMS), design inspection software NAVISWORKS and survey data on site, the accuracy of simulation and verification can be increased, the deviations and non-conformities can be easily found. Through the implementation of this technical scheme, it helps to ensure the smooth and safe implementation of the milestone of dome lifting for nuclear power project. This paper gives an example for combining 3D model and survey on site to simulate dome lifting, methods and suggestions are given for guidance for other projects.

A Dynamic Measurement Model of Equipment Procurement Progress for Nuclear Power Project Based on EVM

2017 ◽  
Author(s):  
Ming Li ◽  
Hui Zhou ◽  
Rongxin Zhang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Dynamic Model ◽  
Nuclear Power ◽  
Cost Control ◽  
Measurement Model ◽  
Dynamic Measurement ◽  
Power Equipment ◽  
Nuclear Power Project ◽  
Power Project

A novel dynamic model and refined method for implementation of the Earned Value Management (EVM) on nuclear power equipment procurement is proposed in this paper. The EVM is known as an efficient and accurate method for progress and cost control in most of the civil engineering systems; however, there is lack of literatures on the EVM for precisely measuring the procurement progress in large-scale complex industrial projects, such as nuclear power plant systems. A novel dynamic measurement model based on the EVM is first established for evaluating the progress and performance of purchasing the nuclear power equipment, including specified details of operating procedure by quantitative valuing each schedule node based on work breaking-down structure (WBS) elements; then the dynamic model is analyzed and verified by a realistic contract of nuclear power equipment procurement. Furthermore, a nuclear power project under construction is studied and the equipment procurement progress is evaluated by applying the novel dynamic measurement model. Finally, the deviation of equipment procurement contract execution is presented by calculating the performance of progress and cost, which helps identify and analyze the delay risks. The dynamic measurement model has been applied in an abuilding nuclear power plant since January 2015, the results of applying the new model providing significant support to the progress and cost control of equipment procurement and bringing considerable profits to the project management. Based on the investigation and results of the above project, the new dynamic model is viable to be employed in future projects of nuclear power plant as a practical reference for applying the EVM in procurement management.

Application of Joint Boring Technique in Solving RCL Wall Thickness Problem

2017 ◽  
Author(s):  
Huadong Zhu
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Wall Thickness ◽  
Nuclear Power ◽  
Coolant Pump ◽  
Reactor Coolant ◽  
Design Requirements ◽  
Nuclear Power Project ◽  
Power Project ◽  
Service Inspection

Nuclear Power Project RCL (reactor coolant loop) is one of the most critical nuclear safety class 1 equipment in PWR nuclear power plant. Filled with borated water, the RCL is a closed loop and serves as pressure boundary incorporating the reactor pressure vessel, steam generator and reactor coolant pump. Since in-service inspection is required for welds of the RCL, the two sides of the welds shall be bored to meet UT (Ultrasonic Testing) inspection requirements. The design standard states that “if the weld is subject to service inspection, the length of the counterbore shall be 2Tmin (Tmin = minimum of wall thickness) for pipe and Tmin for components and fittings. Therefore, the minimal wall thickness of the boring area inside the RCL shall also meet design requirements. Examination of the RCLs delivered to the nuclear power project sites showed that the wall thickness of some parts of the RCL exceed tolerance in varying degrees (the wall thickness is too thin). The RCL borings need to be analyzed to mitigate the negative impact of insufficient wall thickness, maintain RCL wall thickness to the largest extent and meet design requirements. Under the condition of the jobsite data are idealized, this study analyzes the boring plans for the cold leg of loop B at the reactor vessel side for this nuclear power plant Unit 1 NI (Nuclear Island) and discusses the three methods of boring, namely, general boring, taper boring and eccentric boring. It finds that a combination of taper boring and eccentric boring is the optimal plan. This joint boring technique can help achieve the minimal boring wall thickness, reduce the grinding quantity and maintain the required wall thickness, thus resolving the out-of-tolerance issue. In addition, it meets the design requirements, the wall thickness and in-service inspection requirements. Supervision agency approved the application of the joint boring technique to the RCL for the projects. The RCL installation has proved to be a success.

Development of NPP Collaborative Design Management Platform

2017 ◽  
Author(s):  
Shen Jun ◽  
Li Xiaoyan ◽  
Wang Yong
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Collaborative Design ◽  
Nuclear Power ◽  
Research Result ◽  
Basic Function ◽  
Parameters Optimization ◽  
Design Management ◽  
Plant Design ◽  
Management Platform

A collaborative design management platform of Nuclear Power Plant is built by redevelopment on SYSWARE. On the basis of the given overall framework of platform, the realization methods and means of business layers of the platform are discussed in detail. The application example of main parameters optimization of Nuclear Power Plant design is shown, which verifies the basic function of the platform and the feasibility of the knowledge accumulation and reusability. The research result has some reference value for the construction of collaborative design management platform.

scholarly journals Feasibility Study of RNPP (Rooppur Nuclear Power Project) in Bangladesh

2013 ◽  
Vol 05 (04) ◽  
pp. 1526-1530 ◽  
Author(s):  
Tausif Ali ◽  
Iftekhar Zaman Arnab ◽  
Saiful Islam Bhuiyan ◽  
Anik , Rahman ◽  
Iftekhar Hossain ◽  
...  
Keyword(s):  
Feasibility Study ◽  
Nuclear Power ◽  
Nuclear Power Project ◽  
Power Project

Verification of Alarm Displays for the Nuclear Power Plant With Two Modular High-Temperature Gas-Cooled Reactors

2018 ◽  
Author(s):  
Jia Qianqian ◽  
Guo Chao ◽  
Li Jianghai ◽  
Qu Ronghong
Keyword(s):  
High Temperature ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Modular Design ◽  
Early Stage ◽  
Integrated System ◽  
Alarm System ◽  
Control Room ◽  
High Temperature Gas

The nuclear power plant with two modular high-temperature gas-cooled reactors (HTR-PM) is under construction now. The control room of HTR-PM is designed. This paper introduces the alarm displays in the control room, and describes some verification and validation (V&V) activities of the alarm system, especially verification for some new human factor issues of the alarm system in the two modular design. In HTR-PM, besides the regular V&V similar to other NPPs, the interference effect of the alarm rings of the two reactor modules at the same time, and the potential discomfort of the two reactor operators after shift between them are focused. Verifications at early stage of the two issues are carried on the verification platform of the control room before the integrated system validation (ISV), and all the human machine interfaces (HMIs) in the control room, including the alarm system are validated in ISV. The test results on the verification platform show that the alarm displays and rings can support the operators understand the alarm information without confusion of the two reactors, and the shift between the two reactor operators have no adverse impact on operation. The results in ISV also show that the alarm system can support the operators well.

Valves Maintainability Study on Nuclear Power Plant Design Stage

2017 ◽  
pp. 307-313
Author(s):  
Xiaohu Yang ◽  
Jiao Deng ◽  
Hong Jiang ◽  
Lifei Yang ◽  
Wen Chen
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Design Stage ◽  
Plant Design
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