Results 151 to 160 of about 139,532 (201)
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Vibrations of nuclear fuel assemblies: A simplified model

Nuclear Engineering and Design, 1985
Abstract This paper is concerned with the resonance frequencies of nuclear reactor cores. The homogenized equations are obtained by representing the coupled cooling fluid-rod system as an equivalent continuous material. The homogenized dynamical equations are also derived and numerical procedures are presented in brief.
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Temperature measuring analysis of the nuclear reactor fuel assembly

AIP Conference Proceedings, 2014
Study was based on rapid changes of measured temperature values from the thermocouple in the VVER 440 nuclear reactor fuel assembly. Task was to determine origin of fluctuations of the temperature values by experiments on physical model of the fuel assembly.
Urban F.   +4 more
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The DIT Nuclear Fuel Assembly Physics Design Code

Nuclear Science and Engineering, 1988
The DIT code is the Combustion Engineering, Inc. (C-E) nuclear fuel assembly design code. It belongs to a class of codes, all similar in structure and strategy, that may be characterized by the spectrum and spatial calculations being performed in two dimensions and in a single job step for the entire assembly.
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Impact vibrations of guide thimbles in nuclear fuel assembly

Archive of Applied Mechanics, 2016
In nuclear fuel assemblies of pressurized water reactors, guide thimbles (GTs) secure a safe control rod drop. The control rod fall into the GT should be as fast as possible to provide prompt reactor shutdown. The GTs are long thin-walled tubes that are dynamically excited by fuel assembly (FA) components motion caused by pressure pulsations of coolant.
Štěpán Dyk, Vladimír Zeman
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Optimization of mine layout for nuclear fuel assembly storage

Nuclear Engineering and Design, 1982
Abstract The development of a mine layout for a nuclear waste repository in bedded salt is discussed. Optimizations of storage room arrangements and mine arrangements are addressed separately, and a conceptual repository design based on these optimizations is described.
David L. Watson   +3 more
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Research for Crossing Strait Transportation Accident of Nuclear Fuel Assemblies

Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, 2013
Hainan nuclear power plant (HNPP) is the first nuclear power plant built on China’s Hainan Island. Therefore the nuclear fuel assemblies must transport through the Qiongzhou Strait. There are two transportation plans to be used in crossing strait transportation of the fuel assemblies.
Xiaoxiao Xu   +7 more
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Turbulent Heat Transfer with Mixing Vane in Nuclear Fuel Assembly

The KSFM Journal of Fluid Machinery, 2007
The purpose of present work is to analyze the convective heat transfer downstream of mixing vane in subchannel of nuclear reactor with three-dimensional Navier-Stokes equations. SST model is selected as a turbulence closure by comparing the performances of two different turbulent closures. Three different shapes of mixing vane are tested.
Sang-Ho Jung, Kwang-Yong Kim
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Theoretical Heat Transfer Predictions for Finite Nuclear Fuel Rod Assemblies

Nuclear Science and Engineering, 1972
Temperature distributions in an idealized nuclear fuel assembly were computed and studied parametrically.
T. Ginsberg, D. M. France
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Comprehensive Comparison of Nuclear Materials in BNPP Fuel Assemblies

Nuclear Technology, 2023
Zahra Papi, Farrokh Khoshahval
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