scholarly journals Investigation on Two-Phase Flow Characteristics in Nuclear Power Equipment

10.5772/38404 ◽  
2012 ◽  
Author(s):  
Lu Guangyao ◽  
Ren Junsheng ◽  
Huang Wenyou ◽  
Xiang Wenyuan ◽  
Zhang Chengang ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Two Phase Flow ◽  
Flow Characteristics ◽  
Phase Flow ◽  
Power Equipment ◽  
Two Phase

Preliminary Experimental Study on Erosion-Corrosion Behavior of Second Loop Pipeline in Nuclear Power Plant With Vapor Liquid Two Phase Flow

2017 ◽  
Author(s):  
Pengfei Liu ◽  
Xian Zhang ◽  
Nan Zhao ◽  
Junliang Liu ◽  
Bo Kuang
Keyword(s):  
Nuclear Power ◽  
Two Phase Flow ◽  
Flow Characteristics ◽  
Phase Flow ◽  
Water Tank ◽  
Experimental Facility ◽  
Two Phase ◽  
Accelerated Corrosion ◽  
Pressure Water ◽  
Vapor Liquid

Under the conditions of the actual operation of the nuclear power plant, especially in the drainage system of the heaters, water recycling system, and condensate pump recirculation system, there is a sudden pressure drop after the control valve in the pipeline, which will lead to serious vapor-liquid two-phase flow. Vapor liquid two phase flow can lead to accelerated corrosion in the pipeline. In order to study the influence of vapor liquid two phase flow on the accelerated corrosion of the pipeline, an experimental facility for simulating the operating conditions of the Second Loop was designed and completed. The experimental facility comprises a pressure regulator, high pressure water tank, circulating pump, power heater, low pressure water tank, condensing and cooling system, instrumentation and data acquisition system. The flow characteristics and the corrosion characteristics of the inner wall of the pipe in the flow channel after the control value were studied in the experiments. The flow characteristics include the distribution of water and vapor temperature, pressure drop distribution and void fraction along the flow channel. In the meanwhile, the corrosion rate and surface characteristics of inner wall at different locations were also studied by CCD and SEM. In addition, the influences of pipe material and pipeline geometry on the erosion-corrosion were also studied in the experiments.

CFD Investigating the Changes of FAC Wear Sites Due to the Power Uprate of Nuclear Power Plant

2009 ◽  
Author(s):  
Tsun Fu Hung ◽  
Yuh Ming Ferng ◽  
Bing Hong Lin ◽  
Chunkuan Shih ◽  
Bau-Shei Pei
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Two Phase Flow ◽  
Control Volume ◽  
Flow Characteristics ◽  
Piping System ◽  
Phase Flow ◽  
Two Phase ◽  
Simulation Results

Changes of flow-accelerated corrosion (FAC) wear sites on the piping due to the power uprate of nuclear power plant are investigated by way of computational fluid dynamics (CFD) models. These models proposed in this paper include the three-dimensional two-phase flow models and appropriate FAC models. The computations are performed using commercial code Fluent 6.2 which is control-volume-based. A boiling water reactor (BWR), located at Taiwan, is selected in the present analytical works. Simulation results clearly reveal that the present model can precisely capture the two-phase phenomena within the piping system. Coupled with the calculated two-phase flow characteristics, the appropriate FAC indictors can predict the local distributions of severe FAC sites. These predicted results show reasonable agreement with the plant measurements. Therefore, the impacts of power uprate on the changes of wear sites can be confidently investigated by the present CFD model. Through the comparisons of predictions for the selected BWRs under 100%, 105%, and 110% power levels, the simulation results clearly reveal that the power uprate does not significantly change the characteristics of FAC wear sites.

INVESTIGATION OF STRATIFIED WAVY TWO-PHASE FLOW CHARACTERISTICS

Equipment ◽  
2006 ◽  
Author(s):  
Marijus Seporaitis ◽  
S. Gasiunas ◽  
Raimondas Pabarcius
Keyword(s):  
Two Phase Flow ◽  
Flow Characteristics ◽  
Phase Flow ◽  
Two Phase

Investigation of air-water two-phase flow characteristics in a 25.4 mm diameter circular pipe

2021 ◽  
pp. 103813
Author(s):  
Dewei Wang ◽  
Shanbin Shi ◽  
Yucheng Fu ◽  
Kyle Song ◽  
Xiaodong Sun ◽  
...  
Keyword(s):  
Two Phase Flow ◽  
Flow Characteristics ◽  
Circular Pipe ◽  
Phase Flow ◽  
Two Phase

scholarly journals Experimental data for the slug two-phase flow characteristics in horizontal pipeline

Data in Brief ◽  
2018 ◽  
Vol 16 ◽  
pp. 527-530 ◽  
Author(s):  
Abdalellah O. Mohmmed ◽  
Mohammad S. Nasif ◽  
Hussain H. Al-Kayiem
Keyword(s):  
Experimental Data ◽  
Two Phase Flow ◽  
Flow Characteristics ◽  
Phase Flow ◽  
Two Phase

Experimental Study of Two-Phase Flow Induced by Cavitation Through a Safety Relief Valve

2013 ◽  
Author(s):  
Jorge Pinho ◽  
Patrick Rambaud ◽  
Saïd Chabane
Keyword(s):  
Local Minimum ◽  
Two Phase Flow ◽  
Flow Characteristics ◽  
Control Valve ◽  
Recovery Factor ◽  
Phase Flow ◽  
Relief Valve ◽  
Two Phase ◽  
Blow Down ◽  
Choked Flow

The goal of this study is to understand the behavior of a safety relief valve in presence of a two-phase flow induced by cavitation, in which the mass flux tends to be reduced. Two distinct safety relief valves are tested: an API 2J3 type and a transparent model based on an API 1 1/2G3 type. Instead of using a spring, the design of both valves allows the adjustment of the disk at any desired lift. Tests are conducted with water at ambient temperature. Results show a similar influence of cavitation on the flow characteristics of both valves. The liquid pressure recovery factor FL, which is normally used to identify a choked flow condition in a control valve, is experimentally determined in a safety relief valve. The existence of a local minimum located at a height position L/D = 0.14 indicates in this position, a change on the flow characteristics of both valves. It is verified that the existence of a local minimum in the liquid recovery factor is related to the minimum cross section of the flow, which does not remain constant for every lift positions. Furthermore, it is remarked that in the case of the 2J3 safety valve, the blow down ring adjustment has significant influence on the location of the minimum cross sections of the flow.

scholarly journals Two-phase Flow Characteristics in BWRs

2014 ◽  
Vol 28 (2) ◽  
pp. 153-160
Author(s):  
Kenichi KATONO ◽  
Goro AOYAMA ◽  
Takuji NAGAYOSHI ◽  
Kenichi YASUDA ◽  
Koji NISHIDA
Keyword(s):  
Two Phase Flow ◽  
Flow Characteristics ◽  
Phase Flow ◽  
Two Phase
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