Boiling Reactors: A Preliminary Investigation (open access)

Boiling Reactors: A Preliminary Investigation

Technical report detailing kinetic equations that have been developed for a boiling-type reactor and inherent reactor stability studies that have been made on the basis of these equations. Presents features of the proposed reactor, comparisons of circulating types, investigations of bubble-rise velocities, effects of transient conditions of vapor mass in steam chest, and bubble time delay functions yield favorable results. [From Abstract]
Date: December 12, 1951
Creator: Stein, J. M. & Kasten, P. R.
System: The UNT Digital Library
Thorium and Thorium Alloys Preliminary Corrosion Tests (open access)

Thorium and Thorium Alloys Preliminary Corrosion Tests

Technical report investigating the corrosion resistance of thorium and thorium alloys containing from 2 to 6% chromium, columbinium (niobium), titanium, zirconium and titanium-zirconium in distilled water at 95ºC. The true effects of the various alloy additions could not be determined because of the more marked effect of cold working. [From Abstract]
Date: December 19, 1951
Creator: Olsen, Arnold R.
System: The UNT Digital Library
Analysis of Bulk Shielding Facility Neutron Dosimeter Data (open access)

Analysis of Bulk Shielding Facility Neutron Dosimeter Data

Technical report calculating "effective removal cross sections" for Pb, Fe and O from measurements of fast neutron does in the water surrounding the BSF reactor. The values for Pb and Fe agree quite well with those previously determined from Lid tank data, whereas that for O is somewhat lower. [From Abstract]
Date: July 17, 1952
Creator: Podgor, S.
System: The UNT Digital Library
Solution of Experimental Breeder Reactor Slugs (open access)

Solution of Experimental Breeder Reactor Slugs

From abstract: "A full-scale, always-safe, metal dissolver for Experimental Breeder Reactor fuel was designed, built, and installed for test operation. It was found that the dissolver operated satisfactorily, and feasible operating procedures were established for the dissolution of bare, or jacketed, EBR slugs. Minor modifications of the dissolver design have been required to accomodate [sic] a modified EBR slug, but it is believed that this will not significantly affect its operating characteristics."
Date: March 11, 1952
Creator: Sampson, E. M., Jr.
System: The UNT Digital Library
The Hydrolysis of Tributyl Phosphate Ad Its Effect on the Purex Process (open access)

The Hydrolysis of Tributyl Phosphate Ad Its Effect on the Purex Process

From abstract: "The rate of hydrolysis of TBP and the effect of the hydrolysis products in the Purex Process have been studied. Hydrolytic conditions may be encountered in the process which would lead to formation of dibutyl phosphoric acid, causing significant losses of tetravalent plutonium in stripping. This situation may be easily alleviated by reducing and stripping the plutonium in the trivalent state."
Date: December 13, 1951
Creator: Reilly, V. J. & Lanham, W. B.
System: The UNT Digital Library
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
Enrichment of Uranium 236 (open access)

Enrichment of Uranium 236

From abstract: "Neutron-irradiated uranium was electromagnetically separated to provide enrichment of the isotope of mass 236. The final isotopic abundance of U 236 was determined to be 95% in 1800 milligrams of uranium. Useful by-products of the program were 22 grams of 25% U 236 and 1100 grams of 99.7% U 235. These enriched materials have been made available for use on Atomic Energy Commission projects. Possible application of this separation process to recovery of the fuel from the MTR reactor is described."
Date: December 1951
Creator: Harmatz, B.; McCurdy, H. C.; Case, F. N. & Livingston, R. S.
System: The UNT Digital Library
Enrichment of Uranium 236 (open access)

Enrichment of Uranium 236

From abstract: "Neutron-irradiated uranium was electromagnetically separated to provide enrichment of the isotope of mass 236. The final isotopic abundance of U 236 was determined to be 95% in 1800 milligrams of uranium. Useful by-products of the program were 22 grams of 25% U 236 and 1100 grams of 99.7% U 235. These enriched materials have been made available for use on Atomic Energy Commission projects. Possible application of this separation process to recovery of the fuel from the MTR reactor is described."
Date: December 1951
Creator: Harmatz, B.; McCurdy, H. C.; Case, F. N. & Livingston, R. S.
System: The UNT Digital Library
Physics Division Quarterly Progress Report for Period Ending March 20, 1951 (open access)

Physics Division Quarterly Progress Report for Period Ending March 20, 1951

Technical report covering classified work of the Critical Experiments Program in the Physics Division for the period December 20, 1950 to March 20, 1951. Report outlines investigations of properties of critical assemblies composed of uranium and various reflectors and moderators, preliminary measurements of the effective energy for fission in the assembly. [From Introduction and Summary]
Date: July 2, 1951
Creator: Bernstein, S.; Snell, A. H. & Wollan, E. O.
System: The UNT Digital Library
An Investigation of ThF4 - Fused Salt Solutions for Homogeneous Breeder Reactors (open access)

An Investigation of ThF4 - Fused Salt Solutions for Homogeneous Breeder Reactors

Technical report presenting a consideration of the characteristics of fused salt-ThF4 solutions suitable for use in homogeneous reactors. Presented in tandem with a brief survey of the literature pertaining to such solutions and a summary of the experimental work accomplished. [From Abstract]
Date: June 19, 1951
Creator: Blomeke, J. O. & Johnston, C. P.
System: The UNT Digital Library
An Experimental Determination of Fission Product Heating After Shutdown of the Low Intensity Training Reactor (open access)

An Experimental Determination of Fission Product Heating After Shutdown of the Low Intensity Training Reactor

Technical report containing the general arrangement of the Low Intensity Training Reactor and outcomes of experiments that have been performed in the reactor to measure the rate of fission product heat dissipation from the fuel pieces after loss of water. [From Summary, Introduction]
Date: September 25, 1951
Creator: Beall, S. E.
System: The UNT Digital Library
Laboratory Development of the MTR-RaLa Process for the Production of Barium140 (open access)

Laboratory Development of the MTR-RaLa Process for the Production of Barium140

From abstract: "This report presents the laboratory development of the MTR-RaLa Process for the production of barium140 from Materials Testing Reactor assemblies." The laboratory studied four possible chemical schemes with the final process being chosen "on the basis of chemical yield and purity of product, ease of recovery of uranium235, simplicty of equipment, and overall time required for processing" (from introduction).
Date: August 19, 1952
Creator: Blanco, R. E., (Raymond Eugene), 1918-1987; Kibbey, A. H.; Pannell, J. H.; Shank, E. M.; Farmer, J. E.; Helton, D. M. et al.
System: The UNT Digital Library
Chemistry Division Quarterly Progress Report: Period Ending September 30, 1951 (open access)

Chemistry Division Quarterly Progress Report: Period Ending September 30, 1951

This quarterly progress report discusses topics of research and experimentation at the Oak Ridge National Laboratory, including inorganic chemistry, nuclear chemistry, radio-organic chemistry, chemistry of separations processes, chemical physics, radiation chemistry, chemistry of the solid state, instrumentation, reactor chemistry.
Date: September 30, 1951
Creator: Lind, Samuel C., (Samuel Colville), 1879-1965; Boyd, G. E. & Bredig, M. A.
System: The UNT Digital Library
Aircraft Nuclear Propulsion Project Quarterly Progress Report: Period Ending September 10, 1951 (open access)

Aircraft Nuclear Propulsion Project Quarterly Progress Report: Period Ending September 10, 1951

The first part of this quarterly progress report details reactor theory and design, discussing the aircraft reactor experiment, experimental reactor engineering, reactor physics, and critical experiments. The second part of this report is not included. The third part of this quarterly progress report details materials research, discussing corrosion research, physical properties and heat-transfer research, metallurgy and ceramics, chemistry of high-temperature liquids, and radiation damage. The fourth part of this quarterly progress report details alternate systems, discussing a supercritical water reactor, circulating-moderator-coolant reactors. The fifth part of this quarterly progress report includes appendixes.
Date: January 9, 1952
Creator: Briant, R. C.; Ellis, C. B. & Cottrell, William B.
System: The UNT Digital Library
Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960 (open access)

Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960

Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.
Date: February 3, 1961
Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.
System: The UNT Digital Library
Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1952 (open access)

Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1952

This quarterly progress details ongoing research at the Oak Ridge National Laboratory as a part of the Aircraft Nuclear Propulsion Project. Topics discussed include reactor theory and design, [part two is not included], materials research, and appendixes with information on analytical chemical studies.
Date: October 23, 1952
Creator: Briant, R. C.; Buck, J. H.; Miller, A. J. & Cottrell, William B.
System: The UNT Digital Library
Metallurgy of Thorium and Thorium Alloys Interim Report [for] July 1, 1949 to July 1, 1951 (open access)

Metallurgy of Thorium and Thorium Alloys Interim Report [for] July 1, 1949 to July 1, 1951

Technical report containing a comprehensive study of the physical metallurgy of thorium and some of its alloys containing additions of Be, Si, Zr, Ti, Al, Nb, Cr, Mn, and Ce. Melting range, fabricating characteristics, and tensile properties were studied. [From Abstract]
Date: December 7, 1951
Creator: Frye, J. H. & Hamby, D. E.
System: The UNT Digital Library
Mercury Amalgam Bonding of Uranium and Copper (open access)

Mercury Amalgam Bonding of Uranium and Copper

Technical report summarizing one phase of work done to develop methods of bonding uranium to a metal which is a good conductor of heat. Silver was chosen for contact with uranium because it is easy to plate on uranium and there is no danger of brittle Ag-U compounds being formed at elevated temperatures. [From Abstract]
Date: January 22, 1951
Creator: Glasgow, L. G.
System: The UNT Digital Library
The Effect of Fluoride on the Corrosion of Stainless Steel in the Presence of Excess Al+3 Ion (open access)

The Effect of Fluoride on the Corrosion of Stainless Steel in the Presence of Excess Al+3 Ion

Technical report detailing corrosion tests of Type 347 stainless steel for two weeks in boiling uranyl nitrate, sulfuric acid media, with and without additions of Al+3 and F-1 in a 2:1 mole ratio. The results of these tests show that although the presence of aluminum greatly reduces the deleterious effect of fluoride, the corrosion rates are still three to four times greater than when no fluoride is present. [From Abstract]
Date: March 27, 1951
Creator: Olsen, Arnold R.
System: The UNT Digital Library
Production of Fuel Assemblies for the Materials Testing Reactor Mock-Up Critical Experiments (open access)

Production of Fuel Assemblies for the Materials Testing Reactor Mock-Up Critical Experiments

Technical report outlining the fabrication of twenty-five fuel assemblies and three shim-safety rod fuel sections for use in the Materials Resting Reactor Mock-Up Critical Experiments. Results show that two of the assemblies exceeded tolerance in a few of the key dimensions, but were considered acceptable and as a consequence, production was carried out with no rejects. [From Abstract]
Date: April 9, 1951
Creator: Smith, C. D.; Drosten, F. W. & Kerze, F., Jr.
System: The UNT Digital Library
Metallurgy Division Quarterly Progress Report for Period Ending January 31, 1951 (open access)

Metallurgy Division Quarterly Progress Report for Period Ending January 31, 1951

Technical report covering the metallurgy of thorium and on fabrication techniques. Report investigates the stability and corrosion resistance of thorium exposed to eutectic NaK, extrusion as a means of fabrication of thorium tubes or rods, and corrosion of large single metal crystals by liquid metals. [From Summary]
Date: June 7, 1951
Creator: Miller, E. C. & Bridges, W. H.
System: The UNT Digital Library
Metallurgy Division Quarterly Progress Report for Period Ending January 31, 1952 (open access)

Metallurgy Division Quarterly Progress Report for Period Ending January 31, 1952

This quarterly progress report describes the ongoing research at the Metallurgy Division at the Oak Ridge National Laboratory. In particular, this report discusses the thorium research program, the slug problem, the preferred orientation and anisotropy in metals, fundamental studies of alloying, and the ANP program.
Date: August 28, 1952
Creator: Frye, John H., Jr., 1908-2001 & Bridges, W. H.
System: The UNT Digital Library
Metallurgy Division Quarterly Progress Report for Period Ending April 30, 1952 (open access)

Metallurgy Division Quarterly Progress Report for Period Ending April 30, 1952

This quarterly progress report discusses ongoing work at the Metallurgy Division at the Oak Ridge National Laboratory. Topics discussed include thorium research, the preferred orientation of uranium, studies in the ceramics laboratory, the homogenous reactor program, studies in the x-ray laboratory, studies in the metallographic laboratory, the experimental plate-cladding program, and fuel and control element fabrication.
Date: September 22, 1952
Creator: Frye, John H., Jr., 1908-2001 & Bridge, W. H.
System: The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report [for] Period Ending May 15, 1951 (open access)

Homogeneous Reactor Project Quarterly Progress Report [for] Period Ending May 15, 1951

Technical report outlining the reconstitution of the Homogeneous Reactor Experiment Project (HRE) as the Homogeneous Reactor Project. Report covers the need for a broader developmental program to establish the feasibility of obtaining the potential advantages of homogeneous reactors for the production of fissionable materials and power. Details the ultimate objective of the ORNL program to provide the technical information required to determine the feasibility of a full scale plutonium power producing homogeneous reactor. [From Summary]
Date: October 10, 1951
Creator: Swartout, J. A.; Secoy, C. H. & Winters, C. E.
System: The UNT Digital Library