The Application of Ceramics to Hanford Fuel Elements (open access)

The Application of Ceramics to Hanford Fuel Elements

From introduction: This work is a survey of possible uses of ceramic materials in Hanford-type fuel elements.
Date: September 4, 1953
Creator: King, B. W.; Tripp, H. P. & Duckworth, W. H.
System: The UNT Digital Library
Uranium Migration in UO₂-Bearing Ceramics (open access)

Uranium Migration in UO₂-Bearing Ceramics

This report follows a preliminary study on uranium migration in pressed and sintered UO2-bearing bodies based on MoSi2 or Al2O3.
Date: September 4, 1953
Creator: Quirk, J. F.; Smalley, A. K.; Duckworth, W. H. & Ferrell, Edward Francis.
System: The UNT Digital Library
Differential Thermal-Expansion Effects on Brazed Joints (open access)

Differential Thermal-Expansion Effects on Brazed Joints

Abstract: "Differential thermal-expansion effects in brazed joints involving Type 310 stainless steel and GE-62 brazing alloy were investigated. The work included dilation and modulus-of-elasticity measurements using homogenous cast specimens and observations on bimetallic cantilevers made of the two constituents. No anomalies were found, although there were irregularities in the expansion of the brazing alloy which were ascribed to a solubility phenomenon. The elastic modulus of the brazing alloy was determined. Cantilever deflections with temperature and with load were measured, and the results were interpreted using equations which treat the specimens as true bimetals consisting of two homogeneous components. The difference in thermal-expansion coefficients obtained in this way from the temperature-deflection data was consistent with the dilation measurements. The load measurements yielded an average elastic modulus for the bimetal which was about two-thirds of what would have been expected from knowledge of the components. This discrepancy probably arose from porosity which was observed in the braze components."
Date: September 4, 1953
Creator: Saller, Henry A.; Baroody, Eugene Michael, 1914-1982; Deem, H. W.; Stacy, J. T. & Klebanow, H. L.
System: The UNT Digital Library
Fused Salt Mixtures as Potential Liquid Fuels for Nuclear Power Reactors (open access)

Fused Salt Mixtures as Potential Liquid Fuels for Nuclear Power Reactors

From introduction: "This report summarizes the work done on a study of fused-salt systems in a search for new liquid fuels suitable for use in a nuclear power reactor."
Date: September 8, 1953
Creator: Crooks, R. C.; Snyder, M. J. & Clegg, J. W.
System: The UNT Digital Library
Investigation of the Behavior of NaOH-UO₃ Slurries in Small Flow Loops (open access)

Investigation of the Behavior of NaOH-UO₃ Slurries in Small Flow Loops

From introduction: "This report presents the results of an experimental program to evaluate engineering problems which might be encountered when circulating NaOH-UO3 slurry through a thermal cycle."
Date: September 15, 1953
Creator: Stang, J. H.; Lagedrost, J. F.; Simons, E. M. & Dayton, R. W.
System: The UNT Digital Library