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Metallurgy Division Quarterly Progress Report: Period Ending October 31, 1951 (open access)

Metallurgy Division Quarterly Progress Report: Period Ending October 31, 1951

This quarterly progress report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses thorium research, the mechanical properties of metals including thorium, uranium, inconel, and z-nickel, the ANP program (including the following topics: the physical chemistry of liquid metals, and welding research), and the materials testing reactor program.
Date: April 21, 1952
Creator: Frye, John H., Jr., 1908-2001 & Bridges, W. H.
System: The UNT Digital Library
Development of a Cubic Oxide Protective Film on Zirconium (open access)

Development of a Cubic Oxide Protective Film on Zirconium

Observations of the effects of neutron damage to zirconium oxides led to the conclusion that the cubic form of ZrO2 is more stable to such damage than the monoclinic form. It has been reported that zirconium corrodes more rapidly in certain liquids when exposure is made under radiation (neutrons and fission products). It is well known that on heating monoclinic ZrO2 a transformation, monoclinic to tetragonal (very similar to cubic), occurs at about 1500°C. The transformation involves sufficient atomic rearrangement that pieces of ZrO2 normally crack and crumble. It is suggested that the effects of neutrons on monoclinic ZrO2 may be similar so that a protective oxide film on the metal would be destroyed soon after its formation. It might be possible, therefore, that the protective oxide film on zirconium metal which is normally monoclinic might be less resistant to corrosion under radiation damage than a similar film which was cubic.
Date: February 21, 1956
Creator: Johnson, J. R.
System: The UNT Digital Library
HRP Radiation Corrosion Studies (open access)

HRP Radiation Corrosion Studies

A fifth in-pile loop experiment, L-4-8, was completed. The loop operated in-pile for a total of 1637 hr, during which time the LITR energy output was 4377 Mwhr. The average fission power in the loop based o cesium analyses was 622 w when the LITR was at full power (3 Mw). Based on oxygen data, the generalized corrosion rate for the first 300 hr was 4.0 mpy; the rate for the remaining 1357 hr was 0.7 mpy. The nickel data gave parallel results. The corrosion of the type 347 stainless steel, Zircaloy-2, and Ti-55AX [unintelligible] exposed in the core and in in-line holders was generally consistent with that observed in previous in-pile loop experiments. Some differences with steel were attributed to the fact that this was the first loop containing steel specimens operated with 0.04 m H2SO4 present in the uranyl sulfate charge solution (0.17 m UO2SO4, 0.03 m CuSO4). Stress specimens, made from the alloys Zircaloy-2, type 17-4 PH stainless steel, and Ti-C-130-AM, were exposed in care, in-line, and pressurizer locations. Microscopic examination and average weight loss gave no indication of effects attributable to the stressed condition of the specimens.
Date: August 21, 1956
Creator: Baker, J. E.; Bradley, N. C.; Jenks, G. H.; Olsen, A. R.; Savage, H. C. & Walter, F. J.
System: The UNT Digital Library
Large-Scale Slurry-Circulation System, 300-SM (open access)

Large-Scale Slurry-Circulation System, 300-SM

Design philosophy, status of component development, operational procedures, and limitations of each section of the Oak Ridge large-scale, high-temperature, thoria slurry facility.
Date: December 21, 1961
Creator: Parsly, L. F., Jr.; Falkenberry, H. L.; Harley, P. H.; Miller, I. M. & Kenyon, V. L.
System: The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: August-October 1957 (open access)

Homogeneous Reactor Project Quarterly Progress Report: August-October 1957

Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Project. Progress of operations, design, development, and analysis is presented. This report includes tables, illustrations, and photographs.
Date: January 21, 1958
Creator: Briggs, R. B.; Winters, C. E.; Beall, S. E.; Lane, J. A.; Bohlmann, E. G.; Ferguson, D. E. et al.
System: The UNT Digital Library
Molten-Salt Reactor Program Quarterly Progress Report: October 1957 (open access)

Molten-Salt Reactor Program Quarterly Progress Report: October 1957

Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Molten-Salt Reactor Program. Descriptions of the progress and studies conducted is presented. This report includes tables, illustrations, and photographs.
Date: February 21, 1958
Creator: MacPherson, H. G.
System: The UNT Digital Library
Chemical Technology Division Annual Progress Report: for Period Ending June 30, 1962 (open access)

Chemical Technology Division Annual Progress Report: for Period Ending June 30, 1962

Report issued by Oak Ridge National Laboratory that discusses progress and work performed by the Chemical Technology Division.
Date: September 21, 1962
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
System: The UNT Digital Library
Chemical Technology Division Annual Progress Report, May 31, 1961 (open access)

Chemical Technology Division Annual Progress Report, May 31, 1961

Report documenting the ongoing research and developments of the Chemical Technology Division of the Oak Ridge National Laboratory.
Date: September 21, 1961
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
System: The UNT Digital Library
Specifications and Procedures Used in Manufacturing U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor (open access)

Specifications and Procedures Used in Manufacturing U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor

Report containing the description and design of U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor. Topics include the requirements of core materials, materials specifications, manufacturing procedures, and shipping preparation.
Date: October 21, 1963
Creator: Kucera, W. J.; Leitten, C. F., Jr. & Beaver, R. J.
System: The UNT Digital Library
The Technology of Uranium Dioxide a Reactor Material (open access)

The Technology of Uranium Dioxide a Reactor Material

Consideration has been given to various forms of fissionable material for use in atomic reactors, including the pure metals, their alloys and compounds. Of particular interest is the dioxide of uranium which is refractory and corrosion resistant in some environments.The oxide is useful in both granular and bulk forms. Small grains of uranium oxide can be mixed with other materials to form matrix type elements where they serve either as a convenient or necessary form of fuel or fertile material. For other applications the oxide may be fabricated in bulk form such as pellets, rods, plates, or blocks.There is a need for knowledge of the properties of the properties of this oxide, particularly as it affects fabrication in the various forms required. This knowledge is also required by reactor designers and engineers. There is in addition a challenging field for basic studies of sintering rates, oxidation behavior and other phenomena. Fabrication techniques have been developed to produce uranium oxide in various forms with consideration given to the economy of production. The continued application of basic knowledge of these materials has led to simpler. more practical means of fabrication and has thus widened the scope of their use in atomic reactors.
Date: February 21, 1956
Creator: Johnson, J. R.; Doney, L. M.; Fulkerson, S. D.; Taylor, A. J.; Warde, J. M. & White, G. D.
System: The UNT Digital Library
Fluorox Moving-Bed Process for Producing UO3, UF4, and UF6: Bibliography (open access)

Fluorox Moving-Bed Process for Producing UO3, UF4, and UF6: Bibliography

A partial bibliography of reports on the Fluorox moving-bed for producing UO3, UF4, and UF6 is given.
Date: August 21, 1956
Creator: Moore, J. E.
System: The UNT Digital Library