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NACA Research Memorandums
159
Atomic Energy Commission Reports
94
Hanford Works Reports
52
HW (Series)
40
Personal Papers (MS 80-0002)
32
North American Aviation Reports
24
AEC research and development report
20
BMI (Series)
19
Battelle Memorial Institute Reports
19
Hanford Laboratories Operation Monthly Activities Report
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Hanford Laboratories Operation monthly activities report, March 1959
This document details activities of the Hanford Laboratories Operation during the month of March 1959. (FI)
Date:
April 15, 1959
Creator:
unknown
System:
The UNT Digital Library
REACTOR FUEL WASTE DISPOSAL PROJECT PRESSURE-TEMPERATURE EFFECT ON SALT CAVITIES AND SURVEY OF LIQUEFIED PETROLEUM GAS STORAGE
It is deemed feasible to store reactor fuel wastes in a salt dome cavity to a depth where the differential in pressure between the soil over-burden pressure and pressure of the fluid inside the cavity does not exceed 3000 psi, and the temperature is less than 400 deg F. Tests at pressure increments of 1000 psi were conducted on a 2" cylindrical cavity contained in a 6-in. long by 6-in. cylindrical salt core. Tests indicate that the cavity exhibited complete stability under pressures to 3000 psi and temperatures to 300 deg F. At temperatures of 100 to 400 deg F and pressures to 5000 psi continuous deformation of the cavity resulted. Initial movement of the salt was observed at all pressures. This was evidenced by vertical deformation and cavity size reduction. It was noted that a point of structural equilibrium was reached at lower temperatures when the pressure did not exceed 5000 psi. A literature study reveals that the most common type of cavity utilized in liquefied petroleum gas storage is either cylindrical or ellipsoidal. A few are pear or inverted cone shaped. There was no indication of leakage for cavities when pressure tested for as long as 72 hr. …
Date:
January 15, 1959
Creator:
Brown, K. E.; Jessen, F. W. & Gloyna, E. F.
System:
The UNT Digital Library
RELEASE OF FISSION GASES FROM THE AE-6 REACTOR ON MARCH 25, 1959
An analysis was made of the fission-gas-release incident during the pressure pumpdown of the AE-6 Reactor resulting in the contamination of the reactor room and members of the operating staff. Descriptions are given of the normal core pumping procedures, procedural alterations during the incident, the discovery of the contamination and its possible causes, and the remedial actions taken. Steps taken to minimize the chance of the occurrence of the contamination in the future are listed. (B.O.G.)
Date:
April 15, 1959
Creator:
Blackshaw, G.L.
System:
The UNT Digital Library
Progress Report on Waste Concentration Studies: Engineering Results on the BNL Semi-Works Vapor Filtration Vapor Compression Evaporator
Report issued by the Brookhaven National Laboratory discussing progress of waste concentration studies. As stated in the introduction, "the present report covers all experimental hot runs up to the time the still was turned over to the Waste Control Section for intermediate handling of laboratory D waste" (p. 1). This report includes tables, illustrations, and photographs.
Date:
August 15, 1951
Creator:
Horrigan, R. V.; Fried, H. M.; Manowitz, B.; Kuhl, O.; Baranosky, J. A.; Bellanca, S. et al.
System:
The UNT Digital Library
Chemical Research Section Progress Report for January 1950
The following documents are progress reports that follow chemical research studies in subjects such as ruthenium tetroxile distillations, extraction-scrub studies of zirconium and niobium, and oxidation of plutonium and stabilization of plutonium(VI) during extraction of IAF solutions.
Date:
February 15, 1950
Creator:
Albaugh, F. W.
System:
The UNT Digital Library
Environmental Factors at Proposed Site of Dresden Generating Station of Commonwealth Edison Company
From introduction: This report is a compilation of the presently available data pertaining to the proposed reactor power plant site which may be used in evaluating the proposed measures for protecting the public from possible radioactive hazards, both during normal operation and under unusual hazards.
Date:
June 15, 1955
Creator:
Kiefer, W. M.; Chiarottino, M. N.; Geue, D. W.; Veras, A. F. & Bonilla, Charles F.
System:
The UNT Digital Library
Final Report to U.S. Atomic Energy Commission: Low-Temperature Heavy Water Plant
From purpose of report: The primary purpose of this report and its appendices is to transmit to the AEC the principal results of the experimental and engineering work done on the low-temperature process and to describe the factors which led to the designs finally adopted.
Date:
March 15, 1951
Creator:
unknown
System:
The UNT Digital Library
Research and Development Progress Report
"The St. Louis Refinery produced its first UO3 and UO2 in 1942, and its first UF4 and U metal in 1943. The accent has always been on production, and the function of the extremely small research and development groups has been to aid the production units in their job. ... Recently, there has been a growing realization of the need for a broader and more detailed knowledge of both the chemical and technological aspects of all phases of work. ... This is the first of a series of quarterly progress reports on the research and development activities at the St. Louis Refinery."--p. 6
Date:
October 15, 1952
Creator:
unknown
System:
The UNT Digital Library
Final Report on Recovery of Thorium and Uranium From Monazite Sand : Volume 1
Report describing a method for recovery of high yields of thorium and uranium from monazite sand concentrates. Monazite is decomposed into hydrous metal oxides, which are dissolved in an acid. The solution is then separated into a precipitate, which seperates from thorium and uranium. An alternate separation method is evaluated.
Date:
September 15, 1950
Creator:
Calkins, G. D.; Filbert, R. B., Jr.; Bearse, A. E. & Clegg, J. W.
System:
The UNT Digital Library
Final Report on Recovery of Thorium and Uranium From Monazite Sands, Volume 2
From abstract: "Details are presented on the processing of monazite sand and on separating the rare earths from thorium and uranium. Solvent-extraction and ion-exchange techniques for purifying thorium and uranium are described."
Date:
September 15, 1950
Creator:
Calkins, G. D.; Filbert, R. B., Jr.; Bearse, A. E. & Clegg, J. W.
System:
The UNT Digital Library
Estimated Manufacturing Costs for the Recovery of Thorium and Uranium from Monazite Sand
Abstract: "Costs have been estimated for the production of uranium and pure thorium from monasite concentrates by a process involving (1) reaction of monasite with caustic soda, (2) dissolution of the hydrous oxides in hydrochloric acid, (3) separation from the bulk of the rare earths by hydroxide precipitation of thorium and uranium, and (4) purification by solvent extraction."
Date:
September 15, 1950
Creator:
Calkins, G. D. & Filbert, R. B., Jr.
System:
The UNT Digital Library
Progress Report on Refining of MgX and Other Uranium-Bearing Materials
Abstract: "The effects of acidity on extraction of vanadium and molybdenum by diethyl ether are described. Solubility data for several vanadium compounds in nitrate process solutions are presented. Preliminary results on the extraction of uranium from process slurries by tributyl phosphate are reported, including data on the contaminants extracted with the uranium."
Date:
November 15, 1950
Creator:
Ewing, R. A.; Belcher, R. L.; Kiehl, S. J., Jr. & Bearse, A. E.
System:
The UNT Digital Library
Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Seventh Letter Report, April 1 to May 31, 1959
Introduction: "This is the seventh letter report on ARF Project C 127, entitled "Preliminary Studies of Scavenging Systems Related to Radioactive Fallout." This report covers the period from April 1 to May 31, 1959."
Date:
June 15, 1959
Creator:
Stockham, John D. & Rosinski, John
System:
The UNT Digital Library
Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores
Abstract: "Dissolution of carnotite in several readily liquefiable gases, including ammonia, sulfur dioxide, chlorine, and nitrogen dioxide, was found to be negligible, even in the presence of uranium complexing agents. No low-boiling liquids have been found which will dissolve carnotite directly. Treatment with various sulfur chloride will convert carnotite to a form soluble in water or in certain organic solvents. Also, carnotite can be readily dissolved in HCl-acidified ethanol, methanol, or acetone. Amenability tests on nine western ores with HCl-methanol solvent indicated that uranium extractions greater than 90 per cent could be obtained if sufficient acid was used to insure some free acidity in the pregnant liquor. Temple Mountain and Sinbad-Muddy River ores were exceptions to this, uranium extractions being only about 50-60 per cent. Vanadium extractions were invariably lower than uranium extractions. Chemical analyses are presented for nine western ores."
Date:
January 15, 1953
Creator:
Ewing, R. A.; Pobereskin, M.; Kiehl, S. J.; Foley, D. D.; Filbert, Robert B.; Kimball, R. B. et al.
System:
The UNT Digital Library
The Determination of Rare Earths in Thorium
Abstract: "A quantitative method for the determination of individual rare earths in thorium down to a level of 0.05 ppm, is described. The procedure consists of a chromatographic cellulose-columns separation followed by a solution-type spectrographic determination. Values are given for the recovery of a number of rare earths using this combined procedure."
Date:
May 15, 1952
Creator:
Center, E. J.; Henry, W. M. & Householder, R. D.
System:
The UNT Digital Library
The Ammonium Carbonate Pressure Leaching of Uranium Ores Proposed as Feed to the Pilot Plant at Grand Junction, Colorado : Progress Report
From introduction: This is Progress report BMI-282, the first of a series covering the operation of the pressure-leaching towers for the extraction of uranium by an ammonium carbonate leach...This report discusses the data obtained from tests run to show the effects of such variables as the amount of air and carbon dioxide passed through the pulp, temperature, pressure, and concentration of ammonium carbonate and ammonium bicarbonate in the leach solution on the extraction of uranium.
Date:
June 15, 1955
Creator:
Wheeler, C. M.; Langston, B. G. & Stephens, F. M., Jr.
System:
The UNT Digital Library
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
Tungsten-Arc Welding of Ames Thorium and Thorium Alloys
This report follows an investigation made on the welding of Ames thorium by the inert-gas-shielded tungsten-arc process as the first part of a program on the joining of thorium. This program is part of a broader research program to develop the technology of thorium.
Date:
January 15, 1952
Creator:
Monroe, Robert E.; Martin, D. C. & Voldrich, C. B.
System:
The UNT Digital Library
An Application of the Concepts of Particle Packing to the Consolication of Silicon Carbide Powders
From introduction: Silicon carbide is being considered as a basis material for nonmetallic fuel elements because of its high thermal conductivity, low nuclear cross section, high resistance to thermal rupture, and high degree of stability at high temperature in air. A requirement of the fuel elements is that they be thin and have as low porosity as possible. One shape of element under consideration is 0.050 to 0.070 inch thick by a few inches in width and breadth.
Date:
August 15, 1952
Creator:
Harman, Cameron G.; Shinn, J., Jr. & Wagner, H. E.
System:
The UNT Digital Library
Identification of Reaction Products Formed During Magnesium Reduction of Uranium Tetrafluoride: Report
Abstract: "This report describes the results of X-ray diffraction examination of reaction products from a series of experiments performed by Mallinckrodt Chemical Works as an acid in understanding the process of bomb reduction of UF4. UF4 is initially reduced to UF3 by magnesium at 560 C., and subsequently to metal at 600 C. MgF2 from the initial reaction forms a coating on the magnesium which retards the final spontaneous reaction."
Date:
May 15, 1953
Creator:
Schwartz, C. M. & Vaughan, D. A.
System:
The UNT Digital Library
Corrosion-Resistant Materials for Hydrofluoric Acid : Progress Report
Introduction: Among the many corrosion problems encountered in the production of uranium tetrafluoride and uranium metal from ores and concentrates, some of the most serious occur where hydrofluoric acid must be handled.
Date:
June 15, 1953
Creator:
Pray, H. A.; Fink, F. W.; Friedl, B. E. & Braun, W. J.
System:
The UNT Digital Library
Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores
This report describes progress in testing non-aqueous extraction methods for leaching Western ores of uranium and vanadium.
Date:
April 15, 1953
Creator:
Ewing, R. A.; Pobereskin, M.; Kimball, R. B. & Bearse, A. E.
System:
The UNT Digital Library
Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores
The following progress report is part of a series of reports on the study of nonaqueous extractive methods for western uranium ores. This report continues studies on HCl-methanol leaching of Western ores, primarily on Temple Mountain ores.
Date:
July 15, 1953
Creator:
Ewing, R. A.; Pobereskin, M.; Kiehl, S. J.; Foley, D. D.; Filbert, Robert B.; Kimball, R. B. et al.
System:
The UNT Digital Library
Preliminary Report on Thermal and Electrical Conductivities of Some Plutonium-Aluminum Alloys
Abstract: "The thermal and electrical conductivities of a series of Pu-Al alloys have been determined in the range 0.12 atomic percent Pu. The conductivities are approximately proportional to the volume of free aluminum."
Date:
March 15, 1950
Creator:
Gibney, Robert B. & Sandenaw, Thomas A.
System:
The UNT Digital Library