Nuclear Applications · 1968 · 11 citations · 2 references
EngineeringMaterials EngineeringMaterials ScienceEnergy MaterialsMetallurgyNuclear MaterialsNuclear Fuel MaterialsRadiation Damage In MaterialsRadiation-resistant MaterialsSpent Fuel BehaviorIonizing IrradiationIrradiation DamageIrradiation EffectsIrradiation Effects On MaterialsIrradiation SwellingIrradiation-induced Fuel ChangesMicrostructure Evolution Under IrradiationSample Irradiation
Zircaloy-clad specimens of U3Si have been irradiated in pressurized water at rod powers of 480 to 565 W per centimeter of length to burnups of ≈ 5500 MWd/tU. The rate of swelling of the U3Si, which is rapid during the early part of the irradiation, appears to decrease with increasing burnup. The increase in external diameter was much less for these fuel elements than for earlier ones. The improvement is attributed to the provision of a central void which became filled by the U3Si during irradiation.
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Heat transfer coefficient between UO 2 and Zircaloy-2
A.M. Ross, R.L. Stoute · 1962 · 99 citations