Results 261 to 270 of about 167,077 (303)
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Laboratory experiments with impacting fuel rods
Progress in Nuclear Energy, 1995Abstract Vibration surveillance and diagnostics of fuel rods and fuel assemblies are important tasks in NPPs. They are so much the more difficult since the commonly used accelerometers do not operate properly under the extreme conditions of the core of reactor.
S. Kiss, S. Lipcsei
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Quenching and Rewetting of Nuclear Fuel Rods
Nuclear Technology, 1981Many postulated nuclear reactor accidents result in dryout or film boiling within the nuclear core. To minimize fuel rod damage and potential rod failure, safe or lower cladding fuel temperatures must be reestablished by encouraging coolant-cladding contact.
F. S. Gunnerson, T. R. Yackle
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Heat conduction in nuclear fuel rods
Nuclear Engineering and Design, 1985Abstract The numerical solution of the transient heat conduction in the fuel rods of light water reactors is studied in this paper, for the purpose of selecting an efficient, economic and accurate solution procedure to be used in fast running codes.
S.M. Ghiaasiaan +3 more
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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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A Criticism on Fuel Rod Structural Analysis
Nuclear Technology, 1978The state-of-the-art in fuel rod structural analysis is discussed, and possible future developments in this field are outlined. The conclusion is drawn that the most important goal for future research is a deeper understanding of material behavior. It is suggested that a strategy of successive use of diverse models appropriate to the varying degrees of
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Mathematical modeling and analysis of fuel rods
Nuclear Engineering and Design, 1974Abstract This paper presents a comprehensive method of analysis for nuclear fuel rods by first developing appropriate constitutive relations for the fuel and the clad materials that take into account elastic-plastic behavior, primary as well as secondary creep, mechanical densification (hot pressing), fuel swelling, fuel cracking and healing, and ...
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Simulation of Nuclear Fuel Rods by Electrically Heated Rods
Nuclear Technology, 1982Malang, S., Rust, K.
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Testing of a heterogeneous fuel rod in the research Impulse graphite reactor
Progress in Nuclear Energy, 2023Galina Vityuk, Ruslan Irkimbekov
exaly
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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2003
Atomic Energy Society of Japan, Tokyo, Japan ...
LUZZI, LELIO, F. Vettraino, R. Calabrese
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Atomic Energy Society of Japan, Tokyo, Japan ...
LUZZI, LELIO, F. Vettraino, R. Calabrese
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