Results 211 to 220 of about 4,532 (263)
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On the eigenfrequencies of fuel rod vibration in NPPs
Progress in Nuclear Energy, 1992Abstract Eigenfrequencies of fuel pins have been calculated using the fourth order differential equation from mechanics describing beam vibration. Theoretical results have been verified in experiments and comparison of the results is convincing. It was shown that the series of eigenfrequencies follow a quadratic trend.
S. Lipcsei, S. Kiss, G. Pór
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Fuel characteristics required for LWR fuel rod calculations
Journal of Nuclear Materials, 1982Abstract BELGONUCLEAIRE gradually increasing in-reactor experience has enabled to assess the relative importance of attributes defined in specifications and drawings for both UO2 and MO2 fuels. On the basis of that experience, design codes have been benchmarked and were thereafter applied to cover the range of parameters and irradiation histories to ...
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Nonlinear Vibration of Nuclear Fuel Rods
2016From mechanical point of view, nuclear fuel rod (FR) is a complex system consisting of two subsystems—fuel rod cladding (thin walled zirconium tube) and a fuel pellets stack placed inside the cladding placed with a small radial clearance. Both subsystems are beam-type continua that possibly impact-interact during the vibration caused by fuel assembly ...
Š. Dyk, V. Zeman
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A Fuel Rod Debris Packing Model
Nuclear Technology, 1984The nonrandom packing of fuel rod debris around and above the surviving fuel rod segments in a degraded core was analyzed with the spacer grids modeled as a porous floor.
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Simulation of Nuclear Fuel Rods by Electrically Heated Rods
Nuclear Technology, 1982Malang, S., Rust, K.
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The performance capabilities of a National Nuclear Corporation Rod/Sample assay unit was investigated. In conjunction with this, the existing program for on-line data analysis on a Hewlett-Packard 9821A calculator is improved by the use of a least squares curve fit to a quarter sine wave in order to introduce better end corrections.
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A-to-Z Guide to Thermodynamics, Heat and Mass Transfer, and Fluids Engineering, 2006
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Monitoring of Fuel and Cladding Elongation in a Nuclear Fuel Rod
Journal of the Korean Society for Precision Engineering, 2017Jintae Hong +3 more
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Analysis of heat treatment effect on fretting fatigue occurrence in Zr-1Nb-1Sn-0.1Fe fuel rods
Progress in Nuclear Energy, 2021exaly