Defect testing of coextruded uranium-zircaloy-II clad fuel material in a 300 C out-of-reactor recirculating water loop: Interim report
Description:
A major problem in the development of a pressurized water reactor coolant system for the NPS is the rupture performance of the fuel elements. As water temperatures are increased to 300 C, uranium corrosion rates increase rapidly. Swelling of the uranium fuel by corrosion could cause the process tube to burst or reduce the tube cooling water flow below acceptable limits. The desirability of slow cooling of the water to avoid thermal shocks to the reactor piping after a rupture is detected furthe…
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Date:
September 25, 1959
Creator:
Hayden, K. D. & Goffard, J. W.
Partner:
UNT Libraries Government Documents Department