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Nuclear Engineering and Design, 2010
Abstract The grid-to-rod fretting wear-induced fuel rod failure observed in PWRs may be caused by excessive fluid-induced vibration and inadequate fuel rod support by the spacer grid spring. In order to simulate in-reactor grid-to-rod fretting wear behaviors, the grid-to-rod fuel rod supporting conditions as a function of time were predicted by ...
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Abstract The grid-to-rod fretting wear-induced fuel rod failure observed in PWRs may be caused by excessive fluid-induced vibration and inadequate fuel rod support by the spacer grid spring. In order to simulate in-reactor grid-to-rod fretting wear behaviors, the grid-to-rod fuel rod supporting conditions as a function of time were predicted by ...
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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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Nuclear Technology, 1982
For a number of reasons, over the past ten years, much interest has been shown in developing the concept of advanced fuel in liquid-metal fast breeder reactors alongside the classical oxide fuel ro...
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For a number of reasons, over the past ten years, much interest has been shown in developing the concept of advanced fuel in liquid-metal fast breeder reactors alongside the classical oxide fuel ro...
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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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Journal of Nuclear Materials, 1996
Abstract A methodology for fuel rod load follow performance evaluation is presented in this paper. The strain energy density accumulation during one cycle of load follow operation is applied in the cladding fatigue fracture analysis. To combine the energy density increment with critical value for cladding fracture, the cycle number of load follow ...
C.C. Tseng, C.K. Chao
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Abstract A methodology for fuel rod load follow performance evaluation is presented in this paper. The strain energy density accumulation during one cycle of load follow operation is applied in the cladding fatigue fracture analysis. To combine the energy density increment with critical value for cladding fracture, the cycle number of load follow ...
C.C. Tseng, C.K. Chao
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Vibration analysis of PWR fuel rod
Journal of Sound and Vibration, 2005Many reactor components including fuel assembly, heat exchanger tubes and control element assembly are typically beam-type structures with either classical or nonclassical boundary conditions, or both. In such cases, it is quite difficult to evaluate the vibration characteristics of the structures since methods for calculating accurate natural ...
Hyeong Koo Kim, Moon Saeng Kim
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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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Thermographic Imaging of Nuclear Fuel Rods
Nuclear Technology, 1977A method has been demonstrated for imaging details of the fuel-cladding gap region in nuclear fuel rods. The method exploits the geometry-sensitive variation in fuel-cladding gap conductance. After rapid electric resistance heating of the cladding tube by discharge of a capacitor bank, those regions of cladding cool first that have narrow fuel-cladding
Sidney Oldberg +3 more
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