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Atomic Energy Commission Reports
155
United States Geological Survey Reports
117
GJBX
113
United States Department of Energy Grand Junction Office Reports
82
Oak Ridge National Laboratory Reports
60
Trace elements investigations report
51
Hanford Works Reports
50
BNL (Series)
42
Brookhaven National Laboratory Reports
42
University of California Radiation Laboratory Reports
39
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690
Multi-temperature Cross Section Tape for the GNU Multigroup Calculation
A cross section tape has been prepared containing data for elements of most interest for aqueous homogeneous reactor multigroup diffusion calculations involving combinations of 150, 200, 240, 260, and 280°C temperatures. This tape permits multigroup analysis of a reactor in which two or more regions are at different temperatures.
Date:
January 25, 1961
Creator:
Vondy, D. R.
Object Type:
Report
System:
The UNT Digital Library
Uranium-235 Abundance by Gamma Spectrometry
Techniques are described for determining U-235 abundance by measurement of the intensity of 0.18 Mev gamma radiation. One method involves measurement of the ratio of the intensity of 0.18-Mev radiation to that of 0.1 Mev radiation. The preferred technique consists of chemical separation of uranium followed by direct counting of 0.18-Mev photons. Application has been made in analysis of uranium samples of abundances in the range of 0.05% to 93%. Accuracy appears to be better than 3% if the abundance is between 0.7% and 100%. Findings in the self-absorption of 0.18 Mev radiation in uranium oxide are presented.
Date:
January 2, 1957
Creator:
Reynolds, S. A. & Eldridge, J. S.
Object Type:
Report
System:
The UNT Digital Library
The SNAP II Power Conversion System. Topical Report No. 4. Turbine Design and Testing
SNAP II is the designation for a 3 KW nuclear auxiliary power unit to be used in a satellite vehicle. The SNAP II system consists of a reactor heat source, a mercury Rankine engine and an alternator. A two stage, full admission, axial flow turbine was chose for the APU application. Design details and test results are presented in this report. This work was performed under a subcontract to to Atomics International as part of the Atomic Energy Commission Contract No. AT(11-1)-GEN-8.
Date:
January 18, 1960
Creator:
Poulos, Earnest N. & Forman, Edward R.
Object Type:
Report
System:
The UNT Digital Library
Refinements of the Theory of the Infinitely-Long, Self-Acting, Gas-Lubricated Journal Bearing. Interim Report
The lubrication equations for an arbitrary Newtonian fluid are derived directly from the general equations for conservation of mass, momentum, and energy. From the lubrication equations an inequality is obtained for the internal film temperature rise, after which the isothermal film equations are derived. Then, for perfectly-aligned self-acting journal bearings, a conservation equation is obtained. For gas bearings this condition gives: [formula] constant along the axis of the bearing. Application of this condition to the infinitely-long gas bearing gives more accurate pressure solutions for this case. The Katto-Soda form of the differential equation for the infinitely-long bearing is solved by a series expansion in the eccentricity ratio, the first terms of which give the original, approximate Katto-Soda solution. In addition, solutions obtained numerically by digital computations are presented in graphical and tabular form for eccentricity ratios from 0 to 0.9 and compressible bearing parameter [formula]. Design charts based on these calculations are provided.
Date:
January 1960
Creator:
Elrod, Harold G., Jr.
Object Type:
Report
System:
The UNT Digital Library
ORR Startup Accident and Cooling Flow Coastdown Analog Analysis
Startup accident and pump run-down on the ORR have been simulated on the Reactor Controls Analog Facility. At full flow the 150% level scram (45 Mv) easily terminates the startup accident before the metal temperature gets above 180°F. For very low flows typical of criticality runs, temperature coefficients turn the excursion before it reaches 150% of full power, and temperatures climb to boiling, a potentially hazardous condition. (This same behavior can occur at full flow is the power is increased to the point where the level scram must be set above 50 Mw).
Date:
January 4, 1961
Creator:
Stone, R. S. & Colomb, A. L.
Object Type:
Report
System:
The UNT Digital Library
Summary of Runs 1, 2, and 3 in High-Temperature, High-Pressure Titanium Loop
Simulated reactor fuel solutions were circulated at temperatures as high as 365°C in a small titanium pump loop. A hydroclone separator separated heavy phases formed at high temperatures. As the temperature of the solution was increased beyond the two-liquid-phase temperature (327°C), the salt concentration of the light phase decreased and the acid concentration increased. The mole ratios of uranium to sulfate, uranium to copper, and uranium to nickel in the light phase decreased in the same proportion in the temperature range of 330 to 365°C. Corrosion of titanium and Zircaloy-2 specimens was insignificant during the relatively short exposure periods.
Date:
January 6, 1961
Creator:
Griess, J. C.; Baker, J. M. & Savage, H. C.
Object Type:
Report
System:
The UNT Digital Library
Bremsstrahlung Absorption Measurements from Sr^90 TiO3
The absorption in lead of Bremsstrahlung X radiation from a Sr^90 TiO3 pellet in the proximity of Hastelloy "C" was measured. The tenth value layer of the more energetic components of the X-ray continuum was determined to be 1.60 inches.
Date:
January 13, 1961
Creator:
Butler, T. A. & Pierce, E. E.
Object Type:
Report
System:
The UNT Digital Library
Determination of the S. S. N. M. Content of the Shipment to the Davison Chemical Company, Erwin, Tennessee, December 20, 1960
A carrier containing 138.99 liters of solution, uranium concentration 202.04 g/liter with an isotopic concentration of 97.3% U-233, was prepared for shipment. The total uranium was 28,062 +/- 60 g (95% confidence level) and the U-233, 27,305 +/- 66 g (95% confidence level).
Date:
January 11, 1961
Creator:
Sadowski, G. S.
Object Type:
Report
System:
The UNT Digital Library
Revised Version of HFIR Critical Experiment-2 (HFCE-2)
A listing and description is given of the experiments associated with the HFIR Critical Experiment-2. The primary experiments concern the reactivity of the bare core, reactivity worth of "gray" control plates, core-power distribution, reactivity. The secondary experiments concern the reactivity of the fuel, and the reactivity worth of a "partial" gray plate.
Date:
January 16, 1961
Creator:
Kasten, P. R. & Cheverton, R. D.
Object Type:
Report
System:
The UNT Digital Library
Some Heat Transfer Characteristics of ORR Fuel Elements
Analyses are generally made at the ORR with a view toward determining the surface temperatures of fuel plates.
Date:
January 19, 1961
Creator:
Wett, J. F., Jr.
Object Type:
Report
System:
The UNT Digital Library
Sources and Availability of Helium
A review of helium sources, availability, consumption, and future production capacity indicates that the helium consumed in the operation of 100 helium-cooled reactors for 300-Mwe power plants over a 20-year period will run no more than a few per cent of the helium consumed in the U. S. in the next 25 years and less than 1% of the helium that is to be stored during that period under the helium conservation act of 1960 (Public Law 86-777).
Date:
January 19, 1961
Creator:
Fraas, A. P.
Object Type:
Report
System:
The UNT Digital Library
Xenon and Samarium Poisoning
The equilibrium and maximum override values for xenon and samarium poisoning have been computed using the recently issued effective cross sections of C. H. Westcott. Values are given as a function of specific power, neutron temperature, and epithermal flux content.
Date:
January 23, 1961
Creator:
Carlsmith, R. S.
Object Type:
Report
System:
The UNT Digital Library
Pressure Vessel Exposure to Fast Neutrons
In a gas-cooled reactor operating at very high power density the thickness of the reflector may be determine by the requirement that the steel pressure vessel be protected from an excessive dose of fast neutrons, rather than by the usual requirements of neutron economy and power distribution. It is important the the reflector not be made thicker than necessary, since an increase in pressure vessel diameter can result in a marked increase in cost, as well as a decrease in the permitted gas pressure level.
Date:
January 21, 1960
Creator:
Carlsmith, R. S.
Object Type:
Report
System:
The UNT Digital Library
The Measurement Of Free Fission Gas Pressure In Operating Reactor Fuel Elements
The experimental program described has had as its objective the determination of the pressure exerted by free fission gas in operating UO2-filled reactor fuel elements.
Date:
January 23, 1963
Creator:
Reynolds, M. B.
Object Type:
Report
System:
The UNT Digital Library
[Dynamic Test Range 1: Averaged Data]
Geologic, magnetic, and radiometric data collected at Dynamic Test Range - 1 (DTR-1) in Lake Mead, Arizona during an airborne survey for the purpose of developing a calibration standard for airborne gamma-ray detection systems in the National Uranium Resource Evaluation. The data includes concentrations of U, Th, and K in surface materials.
Date:
January 1981
Creator:
L.K.B. Resources, Inc.
Object Type:
Dataset
System:
The UNT Digital Library
[Single Line Data for Dynamic Test Range 1]
Geologic, magnetic, and radiometric data collected at Dynamic Test Range - 1 (DTR-1) in Lake Mead, Arizona during an airborne survey for the purpose of developing a calibration standard for airborne gamma-ray detection systems in the National Uranium Resource Evaluation. The data includes concentrations of U, Th, and K in surface materials.
Date:
January 1981
Creator:
L.K.B. Resources, Inc.
Object Type:
Dataset
System:
The UNT Digital Library
High Power Density Development Project Eleventh Quarterly Progress Report, October-December 1962
Report on progress - fuel development, design of fuel slow system, physics development, and test planning
Date:
January 1, 1963
Creator:
Holladay, R. L.
Object Type:
Report
System:
The UNT Digital Library
Fuel Cycle Program - A Boiling Water Reactor Research and Development Program: Tenth Quarterly Progress Report October-December 1962
The Fuel Cycle Program is an integrated program of investigation in the Vallecitos Boiling Water Reactor and other facilities to improve the technological limits of boiling water reactors in several areas.
Date:
January 14, 1963
Creator:
Howard, C. L.
Object Type:
Report
System:
The UNT Digital Library