scholarly journals ANÁLISE DA OCORRÊNCIA DE DESGASTE POR FRETTING EM VARETAS COMBUSTÍVEIS NUCLEARES DE ZR-1NB-SN-0.1FE / ANALYSIS OF FRETTING WEAR OCCURRENCE ON ZR-1NB-1SN-0.1FE NUCLEAR FUEL RODS

2021 ◽  
Vol 7 (3) ◽  
pp. 30568-30584
Author(s):  
Filipi Gil Cardoso ◽  
Daniele de Azevedo Baêta ◽  
Dionísio José Rodrigues da Costa ◽  
Neil de Medeiros
Keyword(s):  
Nuclear Fuel ◽  
Fretting Wear ◽  
Fuel Rods ◽  
Nuclear Fuel Rods

Mathematical modelling of nonlinear vibration and fretting wear of the nuclear fuel rods

2015 ◽  
Vol 86 (4) ◽  
pp. 657-668 ◽  
Author(s):  
Vladimír Zeman ◽  
Štěpán Dyk ◽  
Zdeněk Hlaváč
Keyword(s):  
Mathematical Modelling ◽  
Nonlinear Vibration ◽  
Nuclear Fuel ◽  
Fretting Wear ◽  
Fuel Rods ◽  
Nuclear Fuel Rods

scholarly journals On Nonlinear Vibration and Fretting Wear of Nuclear Fuel Rods Influenced by Coolant Cross-flow

2017 ◽  
Vol 17 (2) ◽  
pp. 174-179
Author(s):  
Štěpán Dyk ◽  
Vladimír Zeman
Keyword(s):  
Nonlinear Vibration ◽  
Nuclear Fuel ◽  
Cross Flow ◽  
Fretting Wear ◽  
Fuel Rods ◽  
Nuclear Fuel Rods

Evaluation of fretting wear occurrence on the surface of nuclear fuel rods of Zr–1Nb–1Sn-0.1Fe alloy: Effects of assembly misalignment and grid spring loading

Wear ◽  
2020 ◽  
Vol 460-461 ◽  
pp. 203422
Author(s):  
D.A. Baêta ◽  
D.J.R. Costa ◽  
F.G. Cardoso ◽  
N. Medeiros
Keyword(s):  
Nuclear Fuel ◽  
Fretting Wear ◽  
Fuel Rods ◽  
Nuclear Fuel Rods

Probabilistic prediction of fretting-wear damage of nuclear fuel rods

2006 ◽  
Vol 236 (14-16) ◽  
pp. 1628-1640 ◽  
Author(s):  
Pablo R. Rubiolo
Keyword(s):  
Nuclear Fuel ◽  
Fretting Wear ◽  
Probabilistic Prediction ◽  
Fuel Rods ◽  
Nuclear Fuel Rods ◽  
Wear Damage

Inspection of domestic nuclear fuel rods using neutron radiography at the Tehran Research Reactor

2016 ◽  
Vol 58 (9) ◽  
pp. 763-766 ◽  
Author(s):  
Mohammad Hosein Choopan Dastjerdi ◽  
Hossein Khalafi ◽  
Yaser Kasesaz ◽  
Amir Movafeghi
Keyword(s):  
Nuclear Fuel ◽  
Research Reactor ◽  
Neutron Radiography ◽  
Fuel Rods ◽  
Tehran Research Reactor ◽  
Nuclear Fuel Rods

Uncertainty Analysis and Thermal Stored Energy Calculations in Nuclear Fuel Rods

1980 ◽  
Vol 47 (3) ◽  
pp. 457-467 ◽  
Author(s):  
Mitchel E. Cunningham ◽  
Courtney R. Hann ◽  
Anthony R. Olsen
Keyword(s):  
Uncertainty Analysis ◽  
Nuclear Fuel ◽  
Stored Energy ◽  
Fuel Rods ◽  
Energy Calculations ◽  
Nuclear Fuel Rods

Nonlinear Vibrations of Model PWR Fuel Assemblies: Part 2 — Interpretation of Results Using Bilinear Stiffness Model

2020 ◽  
Author(s):  
Prabakaran Balasubramanian ◽  
Giovanni Ferrari ◽  
Giulio M. Franchini ◽  
Marco Amabili ◽  
Kostas Karazis ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Zirconium Alloy ◽  
Nonlinear Boundary ◽  
Nonlinear Boundary Conditions ◽  
Hysteresis Model ◽  
Fuel Rods ◽  
Spacer Grids ◽  
Nuclear Fuel Rods ◽  
Rigid Rod ◽  
Force Displacement

Abstract The experimental response of fuel rods with spacer grids was interpreted using a bilinear hysteresis model. Nonlinear experimental responses of two configurations of rods made out of Zirconium alloy tubes were considered in this paper: one configuration with a single beam and the second configuration with a cluster of beams (stacked in a 3 × 3 matrix formulation). These two configurations were designed to emulate part of the nuclear fuel assembly in Pressurized Water Reactors (PWR). Both configurations were supported by spacer girds at their extremities and were immersed in still water. Spacer grids are grid-like structures made out of thin Zirconium alloy sheets with 17 × 17 cells arranged in a square pattern. Spacer grids provide mechanical support and reduce flow-induced vibration of nuclear fuel rods. They also improve the heat transfer between nuclear fuel rods and the surrounding coolant. The spacer grids impose nonlinear boundary conditions to the beams at the contact points/surface. Specifically, spacer grids present bilinear hysteresis due to their inherent complexity. The bilinear hysteresis shown by spacer grids was measured in terms of force-displacement loops by testing rigid rod inserted in one of its cells. The rigid rod was then excited by external harmonic excitation with excitation frequencies ranging from 5 Hz to 50 Hz in steps of 5 Hz. The bilinear hysteresis model, first studied by Caughey, was modified to include viscous damping and was used to interpret the experimental results. The method of slowly varying parameters was used to solve the equation of motion. First, the measured force-displacement loops of spacer grids were fitted with the numerical model described in the current analysis. Good agreement between the model response and measured loops was found, and the identified parameters allowed the characterization of the nonlinear boundary conditions imposed by spacer grids. Finally, the nonlinear responses of the two configurations under study were interpreted using the bilinear hysteresis model. Excellent agreement between numerical and experimental results was obtained for both configurations.

Research on the nuclear fuel rods melting behaviors by alternative material experiments

2021 ◽  
pp. 153415
Author(s):  
Yonglin Li ◽  
Wenxi Tian ◽  
Ronghua Chen ◽  
Tangtao Feng ◽  
Suizheng Qiu ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Fuel Rods ◽  
Alternative Material ◽  
Nuclear Fuel Rods

Surface Crack Size Detection in Nuclear Fuel Rods Based on Line Structured Light

2020 ◽  
Vol 57 (22) ◽  
pp. 221013
Author(s):  
咸凯强 Xian Kaiqiang ◽  
庞静珠 Pang Jingzhu ◽  
胡俊 Hu Jun
Keyword(s):  
Nuclear Fuel ◽  
Surface Crack ◽  
Structured Light ◽  
Crack Size ◽  
Fuel Rods ◽  
On Line ◽  
Nuclear Fuel Rods
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