FUEL STUDIES UNDER THE SETTLED-BED REACTOR CONCEPT
TL;DRAbstract
Commercially available UC spheres (1/8-in. diameter) prepared by arc melting or powder metallurgy were examined chemically and metallographically and were tested for strength and sodium compatibility. Crushing tests showed that the arc-melted carbide was the stronger of the two. Exposure to NaK at 150 to 760 deg C had no adverse effects on either type of pellet. An in-pile capsule was developed for irradiating pellets in the Brookhaven Graphite Reactor under simulated bed reactor load conditions. (D.C.W.)
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Commercially available UC spheres (1/8-in. diameter) prepared by arc melting or powder metallurgy were examined chemically and metallographically and were tested for strength and sodium compatibility. Crushing tests showed that the arc-melted carbide was the stronger of the two. Exposure to NaK at 150 to 760 deg C had no adverse effects on either type of pellet. An in-pile capsule was developed for irradiating pellets in the Brookhaven Graphite Reactor under simulated bed reactor load conditions. (D.C.W.)
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