Collection
Serial/Series Title
Atomic Energy Commission Reports
175
Hanford Works Reports
64
HW (Series)
49
BNL (Series)
36
Brookhaven National Laboratory Reports
36
General Electric Company Atomic Power Reports
36
GEAP (Series)
33
University of California Radiation Laboratory Reports
24
AECU (Series)
19
Los Alamos National Laboratory Reports
16
47 More
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354 Matching Results
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Occurrence of Technetium in Nature : Final Report for the Period November 1, 1954 to August 31, 1955
Twelve neutron activation analyses for naturally occurring technetium-98 were performed. Positive results were obtained in ten cases. Precautions were taken to avoid interference by molybdenum and technetium-99. the cross section for the reaction [formula] as found to be equal to 4 +- 2 mb for the neutron spectrum of the vertical thimbles of the Argonne CP-5 reactor. The chemical state of molybdenum (VI) in basic solution was studied by an anion-exchange technique. Evidence was obtained for the existence of polymeric species at pH-values up to 14. Preliminary work on the stability of Domax-1 anion exchange resin in perchlorate media indicates rapid deterioration even at 0.2F ClO4-.
Date:
September 1, 1955
Creator:
Anders, Edward, 1926-
System:
The UNT Digital Library
Underground Movement of Radioactive Wastes
The theory and preliminary laboratory investigations presented in this technical report were intended to examine the general feasibility of injection disposal of radioactive wastes and to establish an understanding of the phenomena governing the travel of trace chemicals through natural porous media. Detailed studies of fluid velocity variations resulting from density differences between the injected and displaced liquids have been made. the ion exchange studies have been limited to strontium and calcium. Strontium 90 is considered to be the most hazardous of the fission products and should represent the radioisotope upon which to judge the merits of injection disposal. Consideration should also be given to cesium in evaluation the health hazards of injection disposal.
Date:
August 1, 1955
Creator:
Kaufman, Warren J., 1922-; Orcutt, Richard G., 1924- & Klein, Gerhard, 1918-1987
System:
The UNT Digital Library
A Study of the Delayed Neutron Emitter, Br87
Report discussing a study to determine experimentally whether a low neutron binding energy must be assigned to Kr⁸⁷ to explain the neutron emission or whether the beta-decay energy is especially high, as well as to determine the fission yield of Br⁸⁷.
Date:
August 1, 1950
Creator:
Stehney, Andrew Frank
System:
The UNT Digital Library
Tentative Specification for Waste Heat Steam Boiler
Report discussing specifications for the design of a waste heat steam boiler "for the purpose of generating steam to operate a condensing steam turbine electric generator from the clean hot radioactive air that has cooled the atomic energy reactor of [a] laboratory under a pressure less than atmospheric."
Date:
August 1, 1948
Creator:
Williams, C.
System:
The UNT Digital Library
Ultrasonic Testing of Small-Diameter Tubing
The following report describes the procedure and equipment allowing ultrasonics to be applied successfully to locate flaws in 0.060 in. ID x 0.080 in. OD tubing.
Date:
February 1, 1952
Creator:
Pardus, A. J.
System:
The UNT Digital Library
An Influence Function for the Beta Activity of Uranium(235) Fission Products
Abstract: "Computations have been made of the total beta activity of the fission products arising from the slow neutron fission of U-235. A curve is given exhibiting the activity the activity per unit fission, for time intervals after fission ranging from 0.01 second to 10 years. This influence function is compared with some published experimental data and with the statistical curve of Way and Wigner. A curve facilitates estimation of the activity in the particular case where the fission rate has been constant throughout a known time interval. Finally, an influence function for the particular group of fission products consisting of complete and partial chains having volatile first members is given. This report is based on studies conducted for the Atomic Energy Commission under Contract AT-11-1-GEN-8."
Date:
September 1, 1950
Creator:
Thornton, J. Kendall & Houghton, William J.
System:
The UNT Digital Library
Radium-Barium Separation Process: Part 2 - Chromate Fractionation Procedures
Abstract: A comprehensive study was made of various fractionation systems for the fractional separation of barium-radium mixtures. The most efficient and simplest fractionation scheme was chosen on the basis of the thermodynamics of separating the constituents of mixed crystals and of the combining fractions in a system of repeating composition. This scheme was applied to the separation of barium and radium by utilizing the countercurrent batch fractionation of the chromates. The chromate procedure was evaluated by a comparison with the classic methods which employ the fractional crystallization of the halides. The chromate method is more practical on the basis of radium enrichment per fractionation step, control of precipitating conditions, simplicity, and speed of operation.
Date:
April 1, 1951
Creator:
Salutsky, Murrell Leon; Stites, J. G. & Joy, E. F.
System:
The UNT Digital Library
Determination of half life of polonium-210 by counting: final report
Introduction: "A number of determination have been made of the half life of polonium-210 by calorimetry. Counting affords an entirely different method of determining half lives and requires only a small amount of activity. Therefore for comparison a half-life determination by counting was undertaken with a sample of approximately 0.5 millicurie of polonium."
Date:
June 1, 1951
Creator:
Curtis, Mary Lou
System:
The UNT Digital Library
Processing Tests in Granular Resistance Furnaces for Preparing High Purity Graphite
Report discussing two trial runs for a grannular resistance processing furnace, in which the goal was to produce high purity graphite. These tests were a continuation of a series of trial runs that had previously yielded inconsistent results.
Date:
March 1, 1948
Creator:
Sermon, G. T.
System:
The UNT Digital Library
Molybdenum, Niobium, Tantalum, Tungsten and Uranium Oxide in the Journal Literatures of the USSR :1955 - June 1960
This bibliography lists selected articles on molybdenum, niobium, tantalum, tungsten and uranium oxide in the journal literature of the U.S.S.R. The following sources were used and also are noted after each citation, Special Library Association Translation monthly 1959-June 1960, U.S. Library of Congress Monthly index of Russian accessions 1955-June 1960, U.S. Office of Technical Services Technical translations 1955-1958.
Date:
September 1, 1960
Creator:
Wenrich, Carl J.
System:
The UNT Digital Library
The Preparation of Uranyl Carbonate and Measurement of Its Solubility
From summary: "A method for the preparation of normal uranyl carbonate has been developed. Heretofore, this compound has been known only as a rare, naturally occurring material." The report further discusses the physical properties of the compound, its solubility in water, and its interaction with sodium carbonate.
Date:
August 1, 1949
Creator:
Miller, P. D.; Pray, H. A. & Munger, H. P.
System:
The UNT Digital Library
Physical Constants of Uranium Tetrachloride
Abstract: Exceedingly pure uranium tetrachloride was prepared for use in determining the physical constants of the compound. Measurements were obtained of the melting point and boiling point at pressures ranging from the triple point pressure to atmospheric pressure. Calculations were made of the vapor pressure equation for the liquid, the heat of evaporation, molar boiling point elevation, the vapor pressure equation for the solid, and the critical temperature.
Date:
April 1, 1947
Creator:
Young, H. S. & Grady, H. F.
System:
The UNT Digital Library
The Uranium-Cobalt System
Abstract: "A phase diagram for the uranium-cobalt system has been constructed, based on thermal, microscopic, X-ray and chemical data. The results indicate the existence of three compounds and two eutectics, one of which shows a lowering of the melting point of uranium by approximately 400 C."
Date:
March 1, 1946
Creator:
Noyce, William Knight & Daane, A. H.
System:
The UNT Digital Library
Properties of Tin Oxide: Base Ceramics
From summary: "Various thermal and mechanical properties were measured for sintered tin oxide-matrix compacts which nominally were composed of 99 per cent by weight of tin oxide, SnO2, and one per cent by weight of zinc oxide ZnO...The tin oxide body might be expected to give good service under conditions of severe thermal shock and in an oxidizing atmosphere at temperatures up to 1500°F."
Date:
August 1, 1951
Creator:
Quirk, John F. & Herman, C. G.
System:
The UNT Digital Library
Ozonosphere Observations from Propagation of Atomic Blast Waves
Abstract: "Observations of refracted sound waves from atomic tests at the Nevada and Pacific Proving Grounds are evaluated to show temperature and winds in the ozonosphere. A simplified method of making these interpretations is presented to reduce the computation work load normally associated with atmospheric sound studies."
Date:
October 1, 1954
Creator:
Reed, Jack W.
System:
The UNT Digital Library
Recalculation of Critical Masses of U and Pu Water Tamped Solutions
A report discussing a method of computing the critical mass of U₂₃₅ contained in a water solution confined to a spherical core and surrounded by an infinite water tamper, a modification of said method in which the effect of the resonance fission and absorption is taken into account, and physical constants required to calculate the critical mass using these methods.
Date:
September 1, 1949
Creator:
Greuling, Eugene
System:
The UNT Digital Library
Summary Report for April, May and June, 1951
Report discussing progress made by the Chemistry Division (Section C-1) of the Argonne National Laboratory for the months of April, May and June, 1951. Information is divided into "Nuclear Chemistry and Radiochemistry" and "Basic Chemistry".
Date:
August 1, 1951
Creator:
Manning, W. M. & Osborne, D. W.
System:
The UNT Digital Library
Oak Ridge Static Autoclave Water Decomposition Test
Abstract: "Steady states decomposition product partial pressures of water exposed to an epithermal neutron flux of about 2 x 10-11, at 235F, were 0.4 to 0.65 psi. Recombination studies were made by adding hydrogen and oxygen gases to water under irradiation at different temperature and flux levels. The data show a significant effect of temperature on the rate of pressure drop of the added hydrogen and oxygen. In operating at two flux levels, 1.2 x 10-11 and 2.0 x 10-11, no difference in the rate of pressure drop with flux could be detected with the instrumentation on the test apparatus."
Date:
May 1, 1951
Creator:
Humphreys, J. R., Jr.; Abers, E. L. & Brown, P. E.
System:
The UNT Digital Library
Semi-Annual Progress Report in Metallurgy for the Period October 1, 1950 - March 31, 1951
Report discussing progress made in metallurgy by the Ames Laboratory during the the term from October 1, 1950 to March 31, 1951.
Date:
May 1, 1951
Creator:
Wilhelm, Harley A.
System:
The UNT Digital Library
Semi-Annual Progress Report in Chemistry for the Period October 1,1950--March 31,1951
Report discussing the progress made on various chemistry research projects at Ames Laboratory during the period from October 1, 1950 to March 31, 1951.
Date:
May 1, 1951
Creator:
Ames Laboratory
System:
The UNT Digital Library
The Preparation of Uranium Foil
"Uranium foil 0.001 inch thick was made by rolling cast specimens at 600°C in a steel jacket and cold rolling the resulting 0.012-inch-thick strip to the desired thickness. The foil was of excellent quality, having no pin holes and only very slight cracking."
Date:
October 1, 1948
Creator:
Saller, Henry A. & Keeler, J. R.
System:
The UNT Digital Library
Electrodecontamination of Stainless Steel
Abstract: "In experimental studies, decontamination factors of 1000 to 3000 were obtained by electrostripping deposited radioactivity from stainless steel surfaces, used as the anode, in 2% sulfuric acid at current densities as low as 0.01 amp/in.-2. Stainless steel cathodes were used. The method was successfully applied to contaminated equipment."
Date:
November 1, 1954
Creator:
Bennett, M. R.
System:
The UNT Digital Library
A Study of the Carrier Distillation Excitation of Iron in U3O8
Abstract: "A radioactive tracer, Fe^59, was used to determine the disposition of iron as a result of the excitation of a U3O8 matrix in a d - c arc. Two different spectrographic procedures, both using carrier distillation excitation techniques, were compared as to the percent of iron volatilized, the percent of iron diffused into the electrode and the percent of iron remaining in the residual charge."
Date:
October 1, 1957
Creator:
Atwell, M. G. & Pepper, C. E.
System:
The UNT Digital Library
Results of Experiment 1: FCE Calibration With BORAX Core
Summary: The justification of using polyethylene whose hydrogen density of 0.132 gm/cm³ with a distributed void of 15.9 percent as a mockup of water at 70°F and having a hydrogen density of 0.111 gm/cm³ was tested in the FCE. A mockup close to the BORAX core was built and its critical mass determined. Corrections were calculated for differences in the hydrogen desnity and self shielding of the fuel. The effective FCE critical mass agreed with that of the BORAX core to within one percent.
Date:
October 1, 1956
Creator:
Starr, E. & Toops, Edward Chassell
System:
The UNT Digital Library