Resource Type
Collection
Serial/Series Title
Atomic Energy Commission Reports
1,226
Hanford Works Reports
679
University of California Radiation Laboratory Reports
481
HW (Series)
448
Oak Ridge National Laboratory Reports
372
AECU (Series)
236
Battelle Memorial Institute Reports
193
ORNL (Series)
186
BMI (Series)
183
Los Alamos National Laboratory Reports
175
117 More
Degree Department
Degree Level
Country
States
Decade
Month
3,044 Matching Results
Results open in a new window/tab.
Results:
1 - 24 of
3,044
next
The Theory and Operation of Shock-Load Ferroelectric Transducers
A report discussing "an explosive ferroelectric power supply and the experimental approach followed in determining its operating characteristics."
Date:
November 1959
Creator:
Abegg, M. T.; Kuenning, R. W.; Phelps, P. L., Jr. & Graham, H. M.
Object Type:
Report
System:
The UNT Digital Library
Leaching and Precipitation Tests on Grants Ores
Leaching tests were run on two samples from the Grants area in New Mexico. Uranium extractions of 94 per cent were obtained by leaching Sample 6-1 with solutions containing 240 lbs. of Na2CO3 and 60 lbs. of NaHCO3 per ton and by leaching Sample 6-2 with 270 lbs. of Na2CO3 and 180 lbs. of NaHCO3 per ton. Cyclic tests were completed using caustic precipitation of the leach liquor.
Date:
September 10, 1951
Creator:
Abrams, Charles S. & George, D'Arcy R.
Object Type:
Report
System:
The UNT Digital Library
Preliminary Studies of the Adsorption of Uranium in a Resin-In-Pulp System
Data were obtained in non-flowing and flowing (continuous) batch adsorption systems to serve as a guide to the operating conditions that should be used in a resin-in-pulp adsorption system for the recovery of uranium from ores.
Date:
July 27, 1953
Creator:
Abrams, Charles S. & Kaufman, David
Object Type:
Report
System:
The UNT Digital Library
Preliminary Leaching Tests for the Extraction of Uranium From Various Monticello Stockpile Ores
In a section of the area occupied by the Atomic Energy Commission in Grand Junction, Colorado, a pilot plant is being erected to test a resin-in-pulp process. The process is based on the adsorption of uranium by resin from acid pulps. The first ores to be treated at this plant will be Monticello Stockpile Material. Samples of the various stockpiles sere subjected to a series of leaching, filtering and settling tests, the results of which are presented in this report.
Date:
March 2, 1953
Creator:
Abrams, Charles S.; Moulton, Harry D. & Viklund, Hans I.
Object Type:
Report
System:
The UNT Digital Library
Zirconium Pilot Plant Research and Development Progress Report
The following progress report was compiled by the research and development division of the zirconium pilot plant. This report discusses two iodination and deposition runs that were completed as of August 20, 1951, as well as the third iodination run that uses a vaporizer condenser that condenses approximately 40 pounds of zirconium iodide.
Date:
September 20, 1951
Creator:
Accountius, O. E.; Black, D. G.; Dryden, C. E.; Finney, B. C.; Gruber, B. A.; Jurevic, W. G. et al.
Object Type:
Report
System:
The UNT Digital Library
Instrumentation Flow Plan Symbols and Recommended Drawings : a Standard System for ORNL Instrumentation Applications Work
This report is presented in order to provide a satisfactory system of symbols and identifications for process-instrumentation equipment and to promote a uniformity of practice that will simplify and expedite instrumentation work. It is intended that the systems presented here should be capable of designating and identifying the multitude of instrumentation items which are used for control and operation of conventional processes, as well as for specialized work peculiar to ORNL. Instrument Society of America standards have been adhered to whenever practical.
Date:
February 21, 1958
Creator:
Adams, R. K.; Davis, D. G. & Hyland, R. G.
Object Type:
Report
System:
The UNT Digital Library
Metallurgical Examination of HRT Leak Detector Tubing and Flanges
After several failures had occurred in the HRT leak detector system, several lengths of this tubing were removed for metallurgical examination. The tubing was of type 304 stainless steel and was 1/4" in diameter with a 0.065 wall. The tubing had been purchased as three different lots, the first in 45 ft. lengths and the other two as standards lengths. Tubing from the first lot was used primarily for the shield penetration and, therefore, sections of it are present in all lines of the system. It appears that chloride contamination entered the system in a portion of the first lot of tubing used for the shield penetration. The exact source of the chloride cannot be determined, but after considering the results and visiting the manufacturer's plant, it appears most likely the contamination was during the manufacturing process.
Date:
January 31, 1957
Creator:
Adamson, G. M; Hammond, T. M.; Kegley, T. M. & White, J. K.
Object Type:
Report
System:
The UNT Digital Library
Calculation of k-o in a Uranium-Graphite Lattice
Since the 25 content of the uranium to be used in a MTA multiplying lattice is quite uncertain at present, it is necessary to assume various degrees of depletion in order to estimate the multiplication constant K-o and the production of 49 in an infinite uranium-graphite lattice
Date:
February 8, 1951
Creator:
Adelman, F.
Object Type:
Report
System:
The UNT Digital Library
Energy Spectrum of Deuterons Stripped From He3 and the Resultant Neutron Yield
The attenuation curve of the deuterons stripped from He3 has been measured with a Faraday cup. The corresponding curve at 190 Mev was fit by assuming that the deuterons were monoenergetic, with three processes taking place.
Date:
March 10, 1953
Creator:
Adelman, F. L.
Object Type:
Report
System:
The UNT Digital Library
Three Group Equations for a Multiplying Medium
In the past it was felt that the easiest way to treat a three group equation for a MTA lattice was to solve it without certain terms. This iterative procedure converged rapidly for a medium with depleted uranium fuel, and in fact, a second iteration was not needed.
Date:
June 11, 1952
Creator:
Adelman, F. L.
Object Type:
Report
System:
The UNT Digital Library
Diffusion Equation Green's Functions for Box Problems
The use of diffusion theory to attempt to reproduce the chemical data of Hicks and Stevenson for the spatial distribution of neutrons in a solid block of uranium that is bombarded by 190 Mev neutrons is described.
Date:
December 27, 1951
Creator:
Adelman, F.; Lepore, J. & Rosenblum, M.
Object Type:
Report
System:
The UNT Digital Library
Energy Spectrum of Neutrons from 3-10 MEV
The energy distributions of neutrons in the 3-10 Mev energy range resulting from the bombardment of thin U targets are being investigated by the measurement of proton recoils in photographic plates.
Date:
February 11, 1952
Creator:
Adelman, Frank
Object Type:
Report
System:
The UNT Digital Library
On Neutron Evaporation From Excited Nuclei
At high excitation energies, competition of proton and c-particle emission with neutron emission becomes important. For low excitation, the competition between Y-emission, neutron emission, and fission should be taken into account. To aid in the evaluation of this competition an experiment has been performed to measure the number and energy spectrum of the protons and c-particles emitted in the high energy bombardment of uranium with protons, deuterons, and c-particles.
Date:
June 18, 1953
Creator:
Adelman, Frank L.
Object Type:
Report
System:
The UNT Digital Library
Stability of Florothene Under Exposure to Gamma Radiation
The stability of fluorothene (polytrifluorochloroethylene, Kel-F) to gamma radiation has been investigated to estimate the probable life expectancy of fluorothene equipment exposed to Purex process solutions. Samples of fluorothene were exposed to total gamma radiation dosages up to 10 degree R. The results of these tests substantiate the findings reported by Sisman and Bopp in their compilation of data on the affects of radiation on plastics.
Date:
July 6, 1956
Creator:
Adler, K. L.
Object Type:
Report
System:
The UNT Digital Library
Atmospheric Contamination Associated with Inert-Gas-Shielded, Consumable Electrode Welding
Apparent excessive concentrations of atmospheric contamination which were reported to be associated with an inert-gas-shielded consumable electrode arc wielding operation were studied to evaluate the potential health hazards. A study was made of the concentrations of metal fume and gaseous products of the operation as well as the spectrum of ultraviolet radiation. Recommendations for necessary controls were made.
Date:
July 25, 1955
Creator:
Adley, F. E. & Gill, W. E.
Object Type:
Report
System:
The UNT Digital Library
A Study of Efficiencies and Pressure Drop Characteristics of Air-Filtering Media
Removal of particles from air is discussed in terms of three classes of filtering media--air-sampling, respirator, and air-cleaning. Plots of efficiency versus filtering velocity are presented. The pressure drop characteristics of the filters are discussed in terms of initial pressure drops of the clean filters, variations in pressure drop of the individual filters, and comparison of loading rates.
Date:
August 10, 1953
Creator:
Adley, F. E.; Scott, R. H. & Gill, W. E.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
An anticoincidence gamma ray scintillation spectrometer
From abstract: "A new type of scintillation spectrometer is described. It is designed to suppress signals arising from incident photons that are not completely absorbed in the primary detecting NaI(T1) crystal."
Date:
1952
Creator:
Albert, Richard D.
Object Type:
Report
System:
The UNT Digital Library
Thorex Pilot Plant ; System for Concentrating Second Uranium Cycle Product
A system for concentrating uranyl nitrate solutions was designed and installed in the Thorex Pilot Plant. A total of 16,060 g of uranium was concentrated in the system in 68 batch runs. A total of 14,400 g total uranium (14.180 g U/sup 233/) was recovered as product suitable for shipment. Uranium loss to the evaporator condensate was 0.03% of the total uranium processed. The material balance across the system was 98.4%. The average concentration of uranium in the evaporator feed solution was 29 g/liter; the average concentration in the evaporated solution was 298 g U/liter and in the product solution was 199 g/liter. Radiation readings of bottles containing product solutions were taken with a hard-shell cutie pie immediately after each run, and these readings ranged from 35 to 1100 mr/hr. The radiation levels of the bottles of product solution shipped averaged 78 mr/hr. Bottles of product solution reading in excess of 300 mr/hr, maximum allowable for shipment. were reprocessed in the second-cycle solvent extraction system (Thorex) and reconcentrated. The products from seven runs had radiation levels in excess of 300 mr/hr at the time of concentration, or the activities had grown to that level by the time of shipment. The …
Date:
January 28, 1957
Creator:
Albrecht, W. L.
Object Type:
Report
System:
The UNT Digital Library
Reaction of Hydrogen With Uranium
Report discussing reaction of hydrogen with uranium in a range of temperatures and pressures. Experimental materials, methods and results are included.
Date:
February 17, 1955
Creator:
Albrecht, William M. & Mallett, Manley William, 1909-
Object Type:
Report
System:
The UNT Digital Library
Intermediate Heat Exchanger Preliminary Design. Vol. 1, IHX Preliminary Design
Preface: The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming from the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to a steam generator. Because of this activity the until will be enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shut down it will be necessary to allow time for radioactive decay before the unit will be accessible to personnel. Because of inaccessibility and possible long periods allowed for decay time, it is imperative that the unit give trouble free operation. During periods of shut down, the internals should have easy access for inspection and repair if necessary so that down time is held to a minimum. The general arrangement of the heat exchanger described in this report presents a conventional design utilizing known materials and existing methods of fabrication. In further consideration of all concepts, designs and analyses developed during this period of the program, it is felt that this preliminary design will provide an intermediate sodium heat exchanger of lower cost …
Date:
February 28, 1959
Creator:
Alco Products (Firm)
Object Type:
Report
System:
The UNT Digital Library
Brief Review of Heat Transfer Problems Encountered in the Production of Magnetic Fields
The design of internally cooled electrical coils for the production of high frequency intensity magnetic fields presents many new aspects and combinations of the familiar modes of heat transfer. However, the customary methodology appears to be sufficient for preliminary analysis and understanding of those problems. This methodology comprises the derivation of a qualitative, approximate equation expressing the relative performance of the various parts of a system, followed by an examination of this equation in order to locate the limiting features of the system. These features are then investigated by more powerful methods, which in turn provide guidance for development research in the laboratory.
Date:
May 25, 1959
Creator:
Alexander, L. G.
Object Type:
Report
System:
The UNT Digital Library
Operating Instructions for the UNIVAC Program OCUSOL-A : a Modification of the Eyewash Program
The Eyewash program, written by James H. Alexander and Nancy D. Given, provides solutions of reactor criticality problems in spherical geometry by means of the group diffusion method. It employs thirty lethargy groups (plus one thermal group) in nine regions. The input consists principally of specifying the geometrical scaling factor, boundaries and compositions of the various regions, and temperature level. The output includes the value of vc that would render the system critical, the relative fission density distribution, fissions, absorptions, and leakages in each lethargy group in each region, and, if desired, an edit of the flux at each space point, each lethargy, and an edit of the macroscopic cross sections for each lethargy, each region. OCUSOL-A is a minor modification and extension of Eyewash. It provides for the computation and editing, on the supervisory control typewriter, of the total absorptions in selected nuclides in the various regions. This information is useful in the computation of breeding ratios and the preparation of detailed neutron balances, and in the estimation of flux-averaged cross sections for use in estimating the rate of change of concentration of the various nuclides with burn-up. The program also provides for saving and transferring the final fission …
Date:
June 5, 1957
Creator:
Alexander, L. G.; Carrison, D. A.; Roberts, J. T. & Van Norton, R.
Object Type:
Report
System:
The UNT Digital Library
Information for Application of Gamma Absorptometers for Chemical Processes
Fractional absorption of gamma photons from a source by uranium or plutonium in solution is measured to determine concentration of these elements.
Date:
September 1956
Creator:
Alkire, G. J.
Object Type:
Report
System:
The UNT Digital Library