Kinematic Flow Parameters During Liquid Movement in Pressurized Water Pipelines

Downcomer boiling phenomena in a conventional pressurized water reactor have an important effect on the transient behavior of a postulated large-break LOCA (LBLOCA), because it can degrade the hydraulic head of the coolant in the downcomer and consequently affect the reflood flow rate for a core cooling. To investigate the thermal hydraulic behavior in the downcomer region, a test program for a downcomer boiling is being progressed in the reflood phase of a postulated LBLOCA. For this, the test facility was designed as a one side heated rectangular test section which adopts a full-pressure, full-height, and full-size downcomer-gap approach, but with the circumferential length reduced 47.08-fold. The test was performed by dividing it into two-phases: (I) visual observation and acquisition of the global two-phase flow parameters and (II) measurement of the local two-phase flow parameters on the measuring planes along five elevations. In the present paper, the test results of Phase-I and parts of Phase-II were introduced.

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Experimental study on leakage monitoring of pressurized water pipeline based on fiber optic hydrophone

Water Science & Technology Water Supply ◽

10.2166/ws.2019.116 ◽

2019 ◽

Vol 19 (8) ◽

pp. 2347-2358

Author(s):

Chengchao Guo ◽

Kunming Shi ◽

Xuanxuan Chu

Keyword(s):

Real Time ◽

Fiber Optic ◽

Detection System ◽

Vibration Signal ◽

Monitoring Method ◽

Pressurized Water ◽

Water Pipelines ◽

Back Calculation ◽

Water Pipeline ◽

Leakage Monitoring

Abstract Leakage of water pipelines will significantly endanger the safety operation and service performance of the pipelines. Based on the vibration of pressurized water pipelines deriving from leakage, the BA-FH3200 fiber optic hydrophone (FOH) leakage detection long-term detection system was adopted in prototype tests. The vibration-based real-time leakage monitoring method of the pressurized water pipeline was studied. During the test, the leakage was simulated by opening a spherical valve in the middle of the pipe, and an FOH was placed right above the pipe wall to detect the vibration signal along the pipe. The FOH analysis software was used to monitor the pipeline operation status in real time and acquire data. Then, the data were processed by a self-developed post-processing program, and the parameters were optimized through back-calculation. The test results reveal that the leakage positioning error lay between ±0.07 m, and real-time monitoring (i.e., early warning alarm and leakage positioning) of the FOH for the pressurized water pipeline was feasible.

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The influence of non-uniform blockages on transient wave behavior and blockage detection in pressurized water pipelines

Journal of Hydro-environment Research ◽

10.1016/j.jher.2017.08.002 ◽

2017 ◽

Vol 17 ◽

pp. 1-7 ◽

Cited By ~ 16

Author(s):

H.F. Duan ◽

P.J. Lee ◽

T.C. Che ◽

M.S. Ghidaoui ◽

B.W. Karney ◽

...

Keyword(s):

Transient Wave ◽

Pressurized Water ◽

Water Pipelines

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An Accelerometer-Based Real-Time Monitoring and Leak Detection System for Pressurized Water Pipelines

Pipelines 2016 ◽

10.1061/9780784479957.025 ◽

2016 ◽

Cited By ~ 2

Author(s):

Samer El Zahab ◽

Fadi Mosleh ◽

Tarek Zayed

Keyword(s):

Real Time ◽

Detection System ◽

Leak Detection ◽

Real Time Monitoring ◽

Pressurized Water ◽

Water Pipelines

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Transient Wave-blockage Interaction in Pressurized Water Pipelines

Procedia Engineering ◽

10.1016/j.proeng.2014.02.063 ◽

2014 ◽

Vol 70 ◽

pp. 573-582 ◽

Cited By ~ 10

Author(s):

H.-F. Duan ◽

P. Lee ◽

M. Ghidaoui

Keyword(s):

Transient Wave ◽

Pressurized Water ◽

Water Pipelines

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Studies of turbulent coolant mixing flows in the new generation reactors

MATEC Web of Conferences ◽

10.1051/matecconf/201824509018 ◽

2018 ◽

Vol 245 ◽

pp. 09018

Author(s):

Sergei Dmitriev ◽

Alexander Khrobostov ◽

Maksim Legchanov ◽

Anton Ryazanov

Keyword(s):

Nuclear Reactor ◽

Complex Geometry ◽

Experimental Methodology ◽

Measuring System ◽

Pressurized Water Reactor ◽

Computational Hydrodynamics ◽

Pressurized Water ◽

Experimental Stand ◽

Flow Parameters ◽

New Generation

Due to studying of the flow parameters in the downcomer the bottom plenum of the nuclear reactor can be carried out with the help of CFD programs, the work is devoted to experimental researches in the field of pressurized water reactor with the purpose of creation of benchmarks for verification of domestic codes of computational hydrodynamics. Such data must have high spatial resolution, high resolution and high accuracy of the measurements. It makes necessary to apply complex experimental methodologies, measurement instrumentation and careful adjustment of experimental methodology. So a brief description of the experimental stand and its research methodology is given. A spatial conductometric measuring system that allows to study the processes of turbulent mixing of flows in the complex geometry of the nuclear reactor is presented. The description of experimental research and their results are presented. Conclusions are drawn about the prospects of using spatial conductometry as a vortex-resolving measurement method.

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