scholarly journals Experimental investigation of flow-induced vibration in the control rod guide cylinder of pressurized-water reactor

2019 ◽  
Vol 97 (1) ◽  
pp. 14-22
Author(s):  
Dao-Gang Lu ◽  
Hui-Min Zhang ◽  
Yuan-Peng Wang
Keyword(s):  
Experimental Investigation ◽  
Flow Rate ◽  
Experimental Results ◽  
Pressurized Water Reactor ◽  
Flow Induced Vibration ◽  
Pressurized Water ◽  
Control Rod ◽  
Water Reactor ◽  
Experiment Platform ◽  
Control Rods

An experiment was conducted to investigate flow-induced vibration (FIV) in the control rods of a pressurized-water reactor (PWR). Control rods and a guide cylinder (full scale compared with the real structure) were installed on an FIV experiment platform, with which flow distributions were simulated according to actual situations. The vibration displacements of the control rods were observed in different flow rate ranges of transverse and vertical flows. Several FIV characteristics of the control rods under different transverse and vertical flows were determined by analyzing the experimental results. A formula was also proposed to predict vibration.

Experimental Investigation of the Flow-Induced Vibrations of a Rod Cluster Control Assembly Inside Guides With Enlarged Gaps

2019 ◽  
Author(s):  
Pierre Moussou ◽  
Vincent Fichet ◽  
Luc Pastur ◽  
Constance Duhamel ◽  
Yannick Tampango
Keyword(s):  
Experimental Investigation ◽  
Flow Velocity ◽  
Nuclear Power ◽  
Axial Flow ◽  
Fretting Wear ◽  
Pressurized Water Reactor ◽  
Test Rig ◽  
Pressurized Water ◽  
Control Assembly ◽  
Control Rods

Abstract In order to better understand the mechanisms of fretting wear damage of guide cards in some Pressurized Water Reactor (PWR) Nuclear Power Plant (NPP), an experimental investigation is undertaken at the Magaly facility in Le Creusot. The test rig consists of a complete Rod Cluster with eleven Guide Cards, submitted to axial flow inside a water tunnel. In order to mimic the effect of fretting wear, the four lower guide cards have enlarged gaps, so that the Control Rods are free to oscillate. The test rig is operated at ambient temperature and pressure, and Plexiglas walls can be arranged along its upper part, and a series of camera records the vibrations of the control rods above and below the guide cards. The vertical flow velocity is in the range of a few m/s. Beam-like pinned-pinned modes at about 5 Hz are observed, and oscillations of several mm of the central rods are measured, which come along with impacts at the higher flow velocities. A simple non-linear calculation reveals that the main effect of the impacts between Control Rods and Guide Cards is an increase of the natural frequency of the rods by about 10%. Furthermore, as the vibration spectra collapse remarkably well with the flow velocity, the experiments prove that turbulent forcing is responsible for the large oscillations of the control rods, no other mechanism being involved.

Conceptual design of long‐cycle boron‐free small modular pressurized water reactor with control rod operation

2020 ◽  
Vol 44 (8) ◽  
pp. 6463-6482
Author(s):  
Jaerim Jang ◽  
Jiwon Choe ◽  
Sooyoung Choi ◽  
Matthieu Lemaire ◽  
Deokjung Lee ◽  
...  
Keyword(s):  
Conceptual Design ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Control Rod ◽  
Water Reactor ◽  
Long Cycle

Pressurized Water Reactor Control Rods Worth Calibration Calculation by MCNP

2014 ◽  
Vol 539 ◽  
pp. 684-687
Author(s):  
Bo Yang ◽  
He Xi Wu ◽  
Qiang Lin Wei ◽  
Yi Bao Liu
Keyword(s):  
Neutron Flux ◽  
Flux Density ◽  
Operating Time ◽  
Pressurized Water Reactor ◽  
Reactor Model ◽  
Density Peak ◽  
Pressurized Water ◽  
Water Reactor ◽  
Neutron Flux Density ◽  
Control Rods

Control rods play an important role in nuclear power plant's reactivity control. In this paper, the study first establishes the pressurized water reactor model with Control rods by MCNP program, calculates the reactor keff by KCODE card and neutron flux density by F5:N card. The result shows that when control rods are not inserted, the neutron flux density distribution is similar to the cosine function. The control rods slowly but continuously move up with the reactor's increasing operating time, the neutron flux density peak gradually shifted to the top of reactor core. The simulation results agree with the nuclear fuel management program.

scholarly journals Scram characteristics of control rods of pressurized water reactor under seismic conditions.

1987 ◽  
Vol 30 (267) ◽  
pp. 1450-1457
Author(s):  
Katsuhisa FUJITA ◽  
Yoshikazu SHINOHARA ◽  
Kiyoshi NANBU ◽  
Tetsuto NAKATOGAWA ◽  
Tomonori NOMURA
Keyword(s):  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Control Rods
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