Analysis of the Effect of the Stress-Strain State of Irradiated Zirconium-Alloy Fuel-Element Cladding on Hydride Orientation
Sign Up to like & getrecommendations! Published in 2017 at "Atomic Energy"
DOI: 10.1007/s10512-017-0240-1
Abstract: The effect of the stress distribution on the hydride distribution in zirconium cladding of fuel elements with dispersion fuel is analyzed. It is shown that reorientation of zirconium hydrides can occur in fuel-element cladding under… read more here.
Keywords: fuel; element cladding; effect stress; fuel element ... See more keywords
Sensitivity analysis of a PWR fuel element using zircaloy and silicon carbide claddings
Sign Up to like & getrecommendations! Published in 2017 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2017.05.006
Abstract: Abstract In this paper, the SiC reinforced with Hi-Nicalon type S fibers (SiC HNS) was used as fuel cladding, and its behavior from the neutronic viewpoint was compared with the Zircaloy. To evaluate the average… read more here.
Keywords: fuel; pwr fuel; analysis; fuel element ... See more keywords
Effect of cladding on thermal behavior of nuclear fuel element with non-uniform heat generation
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DOI: 10.1016/j.pnucene.2018.10.013
Abstract: Abstract In nuclear power reactors if the maximum temperature (2000ᵒC) of the fuel element like Uranium-dioxide increments and reaches 2865ᵒC then the fuel element melts down leading to heavy loss and damage. To maintain this… read more here.
Keywords: maximum temperature; heat; fuel element; element ... See more keywords