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Atomic Energy Commission Reports
1,554
Hanford Works Reports
682
University of California Radiation Laboratory Reports
501
HW (Series)
444
BNL (Series)
419
Brookhaven National Laboratory Reports
419
Oak Ridge National Laboratory Reports
400
AECU (Series)
288
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220
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215
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4,190 Matching Results
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Lovely-1, Program No. 55, Thermal Analysis on the IBM 650
This program is intended to be utilized for the establishment of flow requirements of a tailored flow core.
Date:
November 26, 1958
Creator:
Love, J. D. & Stueck, C. J.
Object Type:
Report
System:
The UNT Digital Library
IBM 650 Computer, Program Number 755, Collation of ROC Code Output
Using the output of programs 653 and 654, each card of which contains the dose information for one dose point at one energy, program 655 produces the sum of the dose values of all energies for one dose point
Date:
December 19, 1958
Creator:
Stueck, C. J.
Object Type:
Report
System:
The UNT Digital Library
Reactivity of Substitution Elements
A method is sought for predicting the reactivity differences between fuel elements attached to control absorbers and fixed fuel elements
Date:
January 19, 1959
Creator:
Murray, R. L., Dr.
Object Type:
Report
System:
The UNT Digital Library
Rolling and Welding Type 430M Tubes to Stainless Steel Overlaid Carbon Steel Tubesheets
In the fabrication of the steam generator on APPR-1A it was considered necessary to roll the Type 430M tubes into carbon steel tube-sheets. The rolled joint was a necessary precaution to prevent secondary water from contacting the stainless steel weld.
Date:
February 16, 1959
Creator:
Bennett, R. W.; Meister, R. P. & Kerton, R. J.
Object Type:
Report
System:
The UNT Digital Library
Paper for Glasgow Conference on Nuclear Physics: Cosmotron Production of Heavy Mesons
One might expect that the Cosmotron would offer certain advantages over cosmic rays for the study of heavy unstable particles; provided, of course, that it can produce them. In the first place, the conditions under which they are produced could be controlled to a considerably greater extent. In the second place, it might be possible to arrange conditions under which they would be observed more abundantly, an actual beam of heavy mesons being the ideal situation.
Date:
July 1954
Creator:
Thorndike, A. M.
Object Type:
Report
System:
The UNT Digital Library
Dispersion Strengthening of Iron-Aluminum Base Alloys: A Feasibility Study
The feasibility of improving the mechanical properties at 1700-1800°F of oxidation-resistant Fe-Al-Cr alloys by means of a refractory dispersion has been explored. A literature search was conducted, preliminary experimental determinations of properties of the alloy and its oxides were carried out, and certain mathematical relations between dispersion characteristics and metallurgical variables were derived. The results indicate that the alloys can be strengthened sufficiently by using a dispersion with an interparticle spacing of about 2-3 µ. High-temperature native oxides of the Fe-Al-Cr alloy consist largely of Al2O3 and in theory would serve as a satisfactory second phase.
Date:
December 27, 1960
Creator:
King, Blake
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
Water Treatment in Aqueous Homogeneous Reactors, Experience in HRE-2
A method for water treatment has been developed for corrosion protection in the steam-water cycle of Homogeneous Reactor Experiment No. 2. The use of potassium phosphates for pH control, hydrazine for oxygen removal, and limitation of chlorides in the boiler water to less than 1 ppm has resulted in trouble-free operation of the steam system from December 1957 to December 1960.
Date:
January 4, 1961
Creator:
Neumann, P. D.
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
A Useful Solution for Short Cylindrical Shells and Other Applications
The general solution to the basic differential equation d^4w/dy^4 +4w= -4f(y) is transformed from the primary form treated in most texts to an alternate form in which each integration constant corresponds to one edge condition at y=0. The relationships between the integration constants of the two forms are derived and the values for the transformed functions are tabulated. The particular solution is derived in general and given in unique form for various functional forms of f(y). Matrix notation is used throughout the derivations; however, a knowledge of matrix theory is not need for application of the results.
Date:
February 14, 1961
Creator:
Moore, S. E.
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
Fuel Cycle Program - A Boiling Water Reactor Research and Development Program: Ninth Quarterly Progress Report July 1962 - September 1962
The Fuel Cycle Program is an integrated program of investigation in the Vallecitos Boiling Water Reactor (VBWR) and other facilities to improve the technological limits of boiling water reactors.
Date:
October 25, 1962
Creator:
Howard, C. L.
Object Type:
Report
System:
The UNT Digital Library
High Power Density Development Project Tenth Quarterly Progress Report July-September 1962
The Big Rock Point Reactor of the Consumers Power Company went critical for the first time on September 27, 1962. Summarized here are objectives and accomplishments of the pre-operational period as well as an indication of work scope remaining.
Date:
October 1, 1962
Creator:
Holladay, R. L.
Object Type:
Report
System:
The UNT Digital Library
Heavy Element Isotopic Analysis of UO2 Fuel Irradiated In The VBWR: Report #1
The primary objective of this program is to obtain improved data on the changes in nuclear characteristics with burnup of uranium oxide fuel in a boiling water reactor.
Date:
December 28, 1962
Creator:
Hackney, M. R. & Ruiz, C. P.
Object Type:
Report
System:
The UNT Digital Library
Fabrication of Zirconium Alloys For Specific Zirconium Alloy Design Program
The raw materials and fabrication procedures employed in preparing thirty two zirconium alloy compositions for evaluation as described in GEAP-3979 are reported. Considerations involved in the extension of reported laboratory procedures to larger scale production are discussed.
Date:
December 5, 1962
Creator:
Antony, K. C. & Jones, L. T.
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
Accurate Nuclear Fuel Burnup Analyses: Fourth Quarterly Progress Report September-November, 1962
Work has continued on the development of accurate nuclear fuel burnup analysis. Work performed during the fourth quarter is summarized here.
Date:
December 1, 1962
Creator:
Rider, B. F.; Ruiz, C. P. & Peterson, J. P.
Object Type:
Report
System:
The UNT Digital Library
Two-Phase Pressure Losses Third Quarterly Progress Report August 12-November 12, 1962
This is the third quarterly report on the work done under Contract AT(04-30-189, Project Agreement No.27, and covers the period August 12 to November 12, 1962.
Date:
December 12, 1962
Creator:
Janssen, E. (Engineer) & Kervinen, J. A.
Object Type:
Report
System:
The UNT Digital Library