11 research outputs found
CORRELATIONS BETWEEN SENSITIZATION AND STRESS CORROSION CRACKING OF 300 SERIES STAINLESS STEELS. Progress Report, January-March 31, 1964
Full text linkTHE DEVELOPMENT AND TESTING OF UO FUEL SYSTEMS FOR WATER REACTOR APPLICATIONS. Progress Report, April 1-July 31, 1964
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IRRADIATION TESTING OF CERAMIC FUELS. Interim Report, October 1, 1963 through November 30, 1964
No full textTHE DEVELOPMENT AND TESTING OF UO FUEL SYSTEMS FOR WATER REACTOR APPLICATIONS. Progress Report for Period Ending March 31, 1965
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IRRADIATION TESTING OF CERAMIC FUELS. Summary Report
No full textS>A research program was completed on the composition limits for single- phase face-centered cubic crystal structures in the ZrO/sub 2/-rich region of UO/ sub 2/-CaO-- ZrO/sub 2/ and in the CeO/sub 2/-rich end of UO/sub 2/-- CeO/sub 2/, on the fabrication of highdensity pellets from these cubic compositions of both systems, on the properties of these cubic compositions, and on the irradiation stability of these compositions. Phase studies are reported that confirm the occurrence of cubic regions in both UO/sub 2/-- ZrO/sub 2/-- CaO and UO/sub 2/-- CeO/sub 2/. The properties measured include thermal conductivity, thermal performance testing, melting points, and corrosion in water and steam. Progress in the irradiation program is described. (D. L. C.
THE DEVELOPMENT AND TESTING OF UO FUEL SYSTEMS FOR WATER REACTOR APPLICATIONS. Progress Report, Period Ending, March 31, 1964
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