Numerical simulation of transient overflow characteristics in CCS pump building after the main feed water pipe of SG ruptures

2021 ◽  
Vol 385 ◽  
pp. 111539
Author(s):  
Zijia Chen ◽  
Daogang Lu ◽  
Haiqi Zhao ◽  
Yuhao Zhang
Keyword(s):  
Numerical Simulation ◽  
Feed Water ◽  
Water Pipe

Analysis and Research about the Influences of the Foundation Pit on the Nearby Water Pipe Bridge

2013 ◽  
Vol 838-841 ◽  
pp. 1155-1158
Author(s):  
We Nang Hou ◽  
Fei Ying Liu
Keyword(s):  
Numerical Simulation ◽  
Finite Element ◽  
Three Dimensional ◽  
Water Pipe ◽  
Foundation Pit ◽  
Finite Element Software ◽  
Box Culverts ◽  
Design And Construction

There is a foundation pit of box culverts adjacent to the water pipe bridge of the Dam River in Shenzhen. This text uses large finite element software MIDAS/GTS to do the three-dimensional numerical simulation of pile-earth-supporting anchor, and analyzes the influences on the pipe bridge during the evacuation of the foundation pit with box culverts. This text is on the purpose of providing suggestion for the design and construction of the foundation pit.

scholarly journals Numerical Simulation of Thermal Field in Mass Concrete With Pipe Water Cooling

2021 ◽  
Vol 9 ◽  
Author(s):  
Fuxian Zhu ◽  
Guorong Chen ◽  
Feng Zhang ◽  
Qingwen Li
Keyword(s):  
Numerical Simulation ◽  
Temperature Field ◽  
Heat Dissipation ◽  
New Method ◽  
Mass Concrete ◽  
Water Cooling ◽  
Water Pipe ◽  
Pipe Water ◽  
Control Equation ◽  
Water Pipe Cooling

Water pipe cooling is mainly used to control temperature in the construction of mass concrete structures. It is important to reveal how to accurately stimulate the temperature field of mass concrete under action of this water pipe cooling. This paper presents a new method for this purpose. In this method, the contact surface of the water pipe and the concrete is used as the heat dissipation surface into the control equation and the composite Multiquadrics radial basis function (MQ-RBF) and low-order linear polynomial combination are used to discrete the spatial domain. The heat dissipation surface of the water pipe is included in the boundary conditions so that there is no need to build the refined water pipe modeling. This new method not only reduces the calculation cost but also ensures calculation accuracy. Through four calculation examples, this paper show that the algorithm has advantages in the numerical simulation of the concrete temperature field with water pipe cooling.

Numerical Simulation on Secondary Vortex Rotational Phenomenon for Helically Coiled Water Pipe

2014 ◽  
Vol 687-691 ◽  
pp. 684-687
Author(s):  
Ling Di Tang ◽  
Shou Qi Yuan ◽  
Yue Tang
Keyword(s):  
Numerical Simulation ◽  
Velocity Distribution ◽  
Flow Rate ◽  
Cross Sections ◽  
Internal Flow ◽  
Curvature Radius ◽  
Secondary Vortex ◽  
Water Pipe ◽  
Turbulence Condition ◽  
Secondary Vortices

Helically coiled water pipe is widely used in industry, agriculture and other areas. But few researches have been done on its internal secondary vortex rotational phenomenon. In this paper, the helically coiled water pipe was simulated by CFD software. The secondary vortex structure and its rotational development process in typical cross-sections, and the secondary flow velocity distribution, the axial velocity distribution were researched by numerical simulation. The realizable k-ε model with swirl correction was selected to solve governing equations. It is found that the secondary vortices positions are 45° symmetry in turbulent condition within the range of its working flow rate. The secondary vortices positions vary from vertical symmetry to 45° symmetry when the internal flow of helically coiled pipe translates from laminar condition to turbulence condition. In addition, with the curvature radius increasing, the flow rate that the positions of secondary vortices vary to 45° symmetry will grow up.

Numerical Analysis of Subcooled Water Flashing Flow From a Pressurized Water Reactor Steam Generator Through an Abruptly Broken Main Feed Water Pipe

2019 ◽  
Vol 141 (4) ◽  
Author(s):  
Jong Chull Jo ◽  
Jae Jun Jeong ◽  
Byong Jo Yun ◽  
Jongkap Kim
Keyword(s):  
Flow Field ◽  
Steam Generator ◽  
Feed Water ◽  
Water Pipe ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Subcooled Water ◽  
Numerical Predictions ◽  
Secondary Side

A computational fluid dynamics (CFD) analysis was performed to investigate the hydraulic response of the flow field inside the pressurized water reactor (PWR) steam generator (SG) secondary side and the connected part of main feed water pipe to an abrupt main feed water line break (FWLB) accident. To realistically analyze the transient flow field situation, the flow field was assumed to be occupied initially by highly compressed subcooled water except that the upper part of the SG secondary side where steam occupied as in the practical case and the break was assumed to occur at the circumferential weld line between the feed water nozzle and the main feed water pipe. This would result in a subcooled water flashing flow from the SG through the short-broken pipe end to the surrounding atmosphere, which was numerically simulated in this study. Typical results of the prediction in terms of the fluid transient velocity and pressure were illustrated and discussed. To examine the physical validity of the present numerical simulation of the subcooled water flashing flow, the transient mass flow rates predicted in this study were compared with the other previous numerical predictions based on the subcooled water nonflashing (no phase change) flow or saturated water flashing flow assumptions and the prediction by a simple analysis method.

Numerical Simulation and Analyses of the Loss of Feedwater Transient at the Unit 4 of Kola NPP

2002 ◽  
Author(s):  
Vladimir D. Stevanovic ◽  
Zoran V. Stosic ◽  
Michael Kiera ◽  
Uwe Stoll
Keyword(s):  
Numerical Simulation ◽  
Steam Generator ◽  
Nuclear Power ◽  
Three Dimensional ◽  
Numerical Results ◽  
Coolant Temperature ◽  
Feed Water ◽  
Steam Generation ◽  
Horizontal Steam Generator ◽  
Mass Inventory

A three-dimensional numerical simulation of the loss-of-feed water transient at the horizontal steam generator of the Kola nuclear power plant is performed. Presented numerical results show transient change of integral steam generator parameters, such as steam generation rate, water mass inventory, outlet reactor coolant temperature, as well as detailed distribution of shell side thermal-hydraulic parameters: swell and collapsed levels, void fraction distributions, mass flux vectors, etc. Numerical results are compared with measurements at the Kola NPP. The agreement is satisfactory, while differences are close to or below the measurement uncertainties. Obtained numerical results are the first ones that give complete insight into the three-dimensional and transient horizontal steam generator thermal-hydraulics. Also, the presented results serve as benchmark tests for the assessment and further improvement of one-dimensional models of horizontal steam generator built with safety codes.

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