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Ranken, W.A.; Cronenberg, A.W.
Los Alamos National Lab., NM (USA); Engineering Science and Analysis, Idaho Falls, ID (USA)1984
Los Alamos National Lab., NM (USA); Engineering Science and Analysis, Idaho Falls, ID (USA)1984
AbstractAbstract
[en] A review of irradiation-induced swelling and gas release experience is presented here for the three principal fuels UO2, UC, and UN. The primary advantage of UC and UN over UO2 is higher thermal conductivity and attendant lower fuel temperature at equivalent pellet diameter and power density, while UO2 offers the distinct benefit of well-known irradiation performance. Irradiation test results indicate that at equivalent burnup, temperature, and porosity conditions, UC experiences higher swelling than UO2 or UN. Fission gas swelling becomes important at fuel temperatures above 1320 K for UC, and at somewhat higher temperatures for UO2 and UN. Evidence exists that at equivalent fuel temperatures and burnups, high density UO2 and UN experience comparable swelling behavior; however, differences in thermal conductivity influence overall irradiation performance. The low conductivity of UO2 results in higher thermal gradients which contribute to fuel microcracking and gas release. As a result UO2 exhibits higher fractional gas release than UN, at least or burnups up to about 3%
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1984; 38 p; Symposium on space nuclear power systems; Albuquerque, NM (USA); 10-13 Jan 1984; CONF-840113--10; Available from NTIS, PC A03/MF A01 as DE84016460
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Report
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Conference
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ACTINIDE COMPOUNDS, CARBIDES, CARBON COMPOUNDS, CHALCOGENIDES, DEFORMATION, ENERGY SOURCES, FLUIDS, FUEL PARTICLES, FUELS, MATERIALS, MOBILE REACTORS, NITRIDES, NITROGEN COMPOUNDS, OXIDES, OXYGEN COMPOUNDS, POWER REACTORS, RADIATION EFFECTS, REACTOR MATERIALS, REACTORS, URANIUM COMPOUNDS, URANIUM OXIDES
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