Fuels [nuclear] Development Operation [qtrly rpt, Jan-Mar

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Extra info for Fuels [nuclear] Development Operation [qtrly rpt, Jan-Mar 1961] [declassified]

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T. ER tube-tube fuel elements were irradiated to 3200 MWD/T in a KER Loop. One of the elements with a uranium core failed and a description of the failure was given in the third Quarterly for 1960. (4) Two of the fuel elements had U-2 w/o Zr cores and the post-irradlation examination of the inner tu_q of one such element was reported in the fourth Quarterly for 1960. '"' The outer tube from the U-2 w/o Zr element was examined in a Radiometallugy cell this Quarter. In contrast to the uranium outer tube examined previously, the U-2 w/o Zr outer tube has a smooth surface.

27 x 1014 n/cm2-sec Defect-Testing of Irradiated F) Coextruded Fuel Material - J. W. Goffard A knowledge of the influence of irradiation upon the defect-test behavior of coextruded fuel material is being gained from IRP facility test (IRP= Irradiated Rupture Prototype, an out-of-reactor recirculating, hightemperature, high-pressure irradiated material and decontamination test loop operated by Coolant Systems Development). Coextruded Zircaloy-2 clad uranium fuel rods have been separated from irradiated cluster fuel elements, defected with 0.

The step width, then, must be a compromise between trying to get the welding heat and penetration as far away from the braze as possible, and the width necessary for a good weld profile. At the present time, a step width of I/8 inch is being used with a step height of 3/64 inch. The width of the braze also is a factor in securing a braze free weld. The wider the braze, the more braze will disperse through the weld. 010 inch or below as ideal. Welding voltage is directly proportional to the amount of heat of the weld and thus to the amount of braze in the weld.

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