REACTOR AND MATERIALS TECHNOLOGY DEPARTMENTnQUARTERLY REPORT ON TUNGSTEN-URANIUM DIOXIDE CERMET RESEARCH AND DEVELOPMENT ACTIVITIES JANUARY, FEBRUARY, MARCH, 1965

摘要

Thermally cycled and noncycled W-13. 3 v/o UO2 cermets containing tungsten-coated UO2 were examined by optical and electron microscopy. Tungsten grain boundary and W-UO2 interfacial phases were observed in the cycled cermets.nAfter 45 min at 2500 C in flowing, dry hydrogen, uranium precipitation during cooling of calculated UO2 was considerably less than for pure UO2 or throated UO2.nIntergranular mismatch measurements of an electron beam refined tungsten multicrystal (the source of bicrystal for vapor-sandwich diffusion experiments and high temperature reflection electron microscopy experiments) were completed.