Zirconium Research and Development : Progress Report (open access)

Zirconium Research and Development : Progress Report

From introduction: "This is the ninth monthly report, BMI-514, under Contract No. AT(30-1)-771 on "Zirconium Research and Development". The report covers the work period from September 15, 1950, to October 15, 1950. Work is continuing on the preparation of large-diameter zirconium crystal bars in the 16-inch-diameter de Boer unit. Crystal bars up to 1-5/16 inches in diameter and 8 feet long have been prepared in this unit."
Date: October 15, 1950
Creator: Bulkowski, H. H.; Sebenick, J. J.; Campbell, Ivor E. & Gonser, B. W.
System: The UNT Digital Library
The Fabrication and Compatibility of Metallic Fuel Elements for High-Temperature Service (open access)

The Fabrication and Compatibility of Metallic Fuel Elements for High-Temperature Service

From summary: "This report covers an experimental investigation into the fabrication of various potential fuel-element materials and the testing of these materials for compatibility with structural metals at 1090 C (2000 F)."
Date: October 8, 1951
Creator: Saller, Henry A. & Stacy, J. T.
System: The UNT Digital Library
Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores (open access)

Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores

This report describes progress regarding construction of a small pilot plant and a five-step process involving hydrochloric-sulfuric acid treatment and acetone extraction.
Date: October 20, 1954
Creator: Ewing, R. A.; Foley, D. D.; Filbert, Robert B., Jr. & Bearse, A. E.
System: The UNT Digital Library
Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores (open access)

Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores

This report describes progress in testing nonaqueous extractive methods for leaching Western ores of uranium and vanadium
Date: October 20, 1953
Creator: Ewing, R. A.; Pobereskin, M.; Kimball, R. B. & Bearse, A. E.
System: The UNT Digital Library
A Recirculating Supercritical Water Loop (open access)

A Recirculating Supercritical Water Loop

From Abstract: "A recirculating high-pressure stainless steel loop was developed for the study of heat transfer from small-bore tubes to supercritical water. It was found that under certain conditions, hot spots developed on the test section. The conditions leading to the formation of hot spots were investigated; the results of several runs are tabulated here."
Date: October 25, 1954
Creator: Epstein, H. M.; Goldthwaite, W. H.; Chastain, Joel W. & Fawcett, Sherwood L.
System: The UNT Digital Library
A Recirculating Supercritical Water Loop (open access)

A Recirculating Supercritical Water Loop

From abstract: "A recirculating high-pressure stainless steel loop was developed for the study of heat transfer from small-bore tubes to supercritical water. It was found that under certain conditions, hot spots developed on the test section. The conditions leading to the formation of hot spots were investigated; the results of several runs are tabulated here."
Date: October 25, 1954
Creator: Epstein, H. M.; Goldthwaite, W. H.; Chastain, Joel W. & Fawcett, Sherwood L.
System: The UNT Digital Library
The Effects of Chemical Impurities on the Quality of Rolled Uranium Rod (open access)

The Effects of Chemical Impurities on the Quality of Rolled Uranium Rod

Abstract: "Thirty-four uranium ingots containing controlled amounts of carbon, nitrogen, and Mgl2 slag were cast, rolled, and examined to investigate the relation between these impurities and the quality of the rolled rod. Carbon in concentrations up to 1400 ppm and nitrogen up to 170 ppm, either singly or in combination, had no significant effect on the number of defects observed in the rolled rod. The quality of the rods, however decreased with increasing amount of slag necessary to cause observable differences in the rod could not be detected on analysis, but was visible in the microstructure."
Date: October 1, 1954
Creator: Saller, Henry A.; Keeler, J. R. & Cuddy, L. J.
System: The UNT Digital Library
Welded Closures for Fuel Elements (open access)

Welded Closures for Fuel Elements

From abstract: "The inert-gas metal-arc welding process was used to determine weldability studies of various aluminum alloys that are being considered for use as can materials. The solid-phase and induction welding processes were also investigated for making can closures."
Date: October 8, 1953
Creator: Sopher, R. P.; Martin, G. E.; Grable, G. B.; Voldrich, C. B.; Leatherman, A. F. & Todd, F. C.
System: The UNT Digital Library
The Effectiveness of Spray Cooling (open access)

The Effectiveness of Spray Cooling

Abstract: "A possible method of cooling a liquid-fuel reactor is by spraying liquid metal through the liquid fuel, and then circulating the liquid metal through a heat exchanger. To evaluate the effectiveness of this cooling method, a few simple experiments were made with mercury sprayed through water. On the basis of the results, it was concluded that this method was intrinsically a low-power-density method, which could not find application except where a low fissionable-material inventory was the dominating requirement in a low-power reactor. Even there, it is thought that a boiling homogeneous reactor might be superior. The results are reported, in spite of their probably lack of value in the reactor program, simply to make the record complete."
Date: October 1, 1953
Creator: Dayton, R. W.; Allen, C. M. & Miller, N. E.
System: The UNT Digital Library
Resistance-Welding Methods for End Capping PWR Uranium Oxide Fuel Rods (open access)

Resistance-Welding Methods for End Capping PWR Uranium Oxide Fuel Rods

Report discussing a study of various resistance-welding methods for end capping PWR uranium oxide fuel rods. Flash, upset, and spot welding were all investigated.
Date: October 17, 1955
Creator: Martin, David C.; Kearns, William H. & Pattee, Harry E.
System: The UNT Digital Library
Corrosion in 650 F Degassed Water of Uranium-Molybdenum Alloys Containing Impurity Additions (open access)

Corrosion in 650 F Degassed Water of Uranium-Molybdenum Alloys Containing Impurity Additions

From introduction: "At the request of WAPD, a study has been made of the effect of minor compositional variables on the corrosion behavior of uranium-molybdenum alloys in 650 F degassed water."
Date: October 6, 1955
Creator: Cawthorne, Edward W.; Berry, Warren E., 1922-; Reynolds, James E.; Jaffee, Robert Isaac, 1917- & Peoples, Robert S.
System: The UNT Digital Library
The Characteristics of the Bond Interface Formed Between Zircaloy 2 and Uranium-12 w/o Molybdenum (open access)

The Characteristics of the Bond Interface Formed Between Zircaloy 2 and Uranium-12 w/o Molybdenum

The following report analyzes the results taken from studies on the characteristics of the bond interface formed between zircaloy 2 and uranium-12 w/o molybdenum alloys.
Date: October 17, 1955
Creator: Saller, Henry A.; Paprocki, Stan J. & Hodge, Edwin S.
System: The UNT Digital Library
Effects of Ternary Additions on Aluminum-35 w/o Uranium Alloys (open access)

Effects of Ternary Additions on Aluminum-35 w/o Uranium Alloys

Abstract: "The effects of a number of ternary additions on the constitution, casting, and fabricating characteristics and the physical properties of aluminum-35 w/o uranium were investigated. Initial investigations were concerned with the effects of 3 w/o ternary additions on the microstructure and press-forging characteristics of the alloy. It was found that additions of this magnitude often introduced extrinsic phases in the alloy. At the 3 w/o level, additions of germanium, silicon, tin or zirconium inhibited the formation of UAl4 and thereby increased the content of the aluminum matrix in the alloy. It was also noted that these additions decreased the pressures required for extruding, and the tin addition also improved the homogeneity of cast shapes. Lead and palladium also improved the homogeneity of the cast material; however, neither of these was an effective inhibitor of UAl4 and free lead was detected in the alloy to which lead had been added at the ternary. From these studies it appears that tin and zirconium are as effective as silicon in enhancing the fabricating characteristics of aluminum-35 w/o uranium alloys, and may prove superior when evaluated on the bases of casting qualities and recycling characteristics."
Date: October 27, 1959
Creator: Daniel, Norman E.; Foster, Ellis L. & Dickerson, Ronald F.
System: The UNT Digital Library
High-Temperature Oxidation Resistance of Thin Iron-Chromium-Aluminum Alloy Sheet (open access)

High-Temperature Oxidation Resistance of Thin Iron-Chromium-Aluminum Alloy Sheet

Abstract: "The oxidation resistance of thin sheets of iron-28 w/o chromium-2.67 to 10.0 w/o alloys, nominally 0.004, 0.006, 0.008, 0.012, and 0.016 in. thick, was determined by exposure in static air for 100 hr at 2100 and 2300 F. A minimum of 3.67 and 9.37 w/o aluminum was necessary to prevent excessive oxidation of 0.004-in.-thick sheet material at 2100 and 2300 F, respectively. Correspondingly, specimens of lower aluminum content and greater thickness withstood the oxidation attack. Oxidation of iron-chromium-aluminum alloys appeared to be related to the diffusion of aluminum to surfaces of the sheet to form an adherent protective layer of Al2O3."
Date: October 22, 1957
Creator: Jablonowski, Edward J.; Shober, Frederic R. & Dickerson, Ronald F.
System: The UNT Digital Library
Neutron-Flux Measurements in a Flat Plat Fuel Element (open access)

Neutron-Flux Measurements in a Flat Plat Fuel Element

The following report presents neutron-flux measurements with the Mark I element, which include neutron-flux distribution and flux depression within the element.
Date: October 31, 1957
Creator: Morgan, Walter R.; Anno, James N., Jr. & Chastain, Joel W., Jr.
System: The UNT Digital Library
Shielding Studies on Salt Slabs, Gadolinium, and Water (open access)

Shielding Studies on Salt Slabs, Gadolinium, and Water

Review of a study regarding a lid-tank shielding facility's properties, including fast-neutron and gamma dose rates and thermal-neutron fluxes, which were mapped in a symmetry plane. The removal cross section of gadolinium was determined through comparison with various other materials.
Date: October 7, 1959
Creator: Klingensmith, Raymond W.; Epstein, Harold M. & Chastain, Joel W.
System: The UNT Digital Library