The Irradiation Behavior of ZrO2 - UO2
Author : B. F. Rubin
Publisher :
Page : 228 pages
File Size : 31,36 MB
Release : 1962
Category : Uranium oxides
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Author : B. F. Rubin
Publisher :
Page : 228 pages
File Size : 31,36 MB
Release : 1962
Category : Uranium oxides
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Author :
Publisher :
Page : pages
File Size : 29,84 MB
Release : 1962
Category :
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Twelve 0.22-in.-diameter fuel specimens containing a longitudinal central vent and clad with 0.010 in. of Type 304 stainless steel were irradiated to evaluate the effect of restraint and a central vent on fuel element stability. The cladding of 10 of the specimens contained porous end plugs to vent any released fission gas and thus to minimize the buildup of gas pressure within the stainless steel cladding. The specimens consisted of a 20% enriched uranium--2 wt% zirconium alloy core surrounded by a natural uranium--2 wt% zirconium alloy sleeve. Eight of the specimens were irradiated to burnups of the enriched core of 6.9 to 12.8% of all atoms (1.2 to 2.2 at.% of the duplex assembly) at maximum fuel temperatures ranging from 280 to 760 deg C. Most of the clad specimens exhibited negligible volume increases as a result of irradiation. Two specimens containing central vents but unclad were irradiated together with the clad specimens in an attempt to differentiate between the effects due to a central vent and the effects due to cladding. The central vent in itself did not appear to reduce the swelling characteristics of the alloy. Mechanical restraint appeared to have extended the useful operating temperatures of the metallic fuel alloy by at least 200 deg C and also greatly extended the burnup levels to which the fuel could be irradiated. (auth).
Author : J. A. Horak
Publisher :
Page : 46 pages
File Size : 49,4 MB
Release : 1962
Category : Irradiation
ISBN :
Twelve 0.22-in.-diameter fuel specimens containing a longitudinal central vent and clad with 0.010 in. of Type 304 stainless steel were irradiated to evaluate the effect of restraint and a central vent on fuel element stability. The cladding of 10 of the specimens contained porous end plugs to vent any released fission gas and thus to minimize the buildup of gas pressure within the stainless steel cladding. The specimens consisted of a 20% enriched uranium--2 wt% zirconium alloy core surrounded by a natural uranium--2 wt% zirconium alloy sleeve. Eight of the specimens were irradiated to burnups of the enriched core of 6.9 to 12.8% of all atoms (1.2 to 2.2 at.% of the duplex assembly) at maximum fuel temperatures ranging from 280 to 760 deg C. Most of the clad specimens exhibited negligible volume increases as a result of irradiation. Two specimens containing central vents but unclad were irradiated together with the clad specimens in an attempt to differentiate between the effects due to a central vent and the effects due to cladding. The central vent in itself did not appear to reduce the swelling characteristics of the alloy. Mechanical restraint appeared to have extended the useful operating temperatures of the metallic fuel alloy by at least 200 deg C and also greatly extended the burnup levels to which the fuel could be irradiated.
Author :
Publisher :
Page : 852 pages
File Size : 50,32 MB
Release : 1974
Category : Nuclear energy
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Author :
Publisher :
Page : 918 pages
File Size : 15,7 MB
Release : 1972
Category : Nuclear energy
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Author :
Publisher :
Page : 92 pages
File Size : 13,78 MB
Release : 1963-10
Category : Nuclear reactors
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Author : R. G. Gray
Publisher :
Page : 126 pages
File Size : 32,26 MB
Release : 1963
Category :
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Author : I. Cohen
Publisher :
Page : 80 pages
File Size : 10,50 MB
Release : 1962
Category : Uranium compounds
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Author : D. I. Sinizer
Publisher :
Page : 52 pages
File Size : 18,72 MB
Release : 1962
Category : Nuclear fuels
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Author :
Publisher :
Page : 1330 pages
File Size : 18,17 MB
Release : 1971
Category : Aeronautics
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