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Homogeneous Reactor Project Quarterly Progress Report: November 1959-January 1960
From Summary: "The major objective of the run was the investigation of fuel stability. The reactor operated for long periods at the design power of 5 Mw with none of the usual indications of instability while the system pressure was kept at 1250 psig. Run 21 ended on January 22, so that the reason for an abrupt change in the mixing rate of fuel between the core and blanket could be investigated and a reactor steam-system valve could be repaired."
Date:
April 29, 1960
Creator:
Briggs, R. B.
System:
The UNT Digital Library
Mathematics Panel: Annual Progress Report for Period Ending December 31, 1960
Programming research in the construction of a translator to Oracle language from ALGOL.
Date:
April 6, 1961
Creator:
unknown
System:
The UNT Digital Library
Quarterly Progress Report Metallurgy Research Operation: October, November, December, 1964
Quarterly progress report on metallurgy research operations at Hanford Atomic Products Operation in Richland, Washington.
Date:
April 27, 1965
Creator:
unknown
System:
The UNT Digital Library
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 2, Concept I System Description
From introduction: "This report has been prepared in conjunction with the Liquid Metal Fast Breeder Reactor (LMFBR) Follow-On Study. It is the Concept I description of Task I as outlined by Argonne National Laboratory (ANL) in Appendix C of their Follow-On Study Program."
Date:
April 1967
Creator:
Boyer, R. L.
System:
The UNT Digital Library
Floating-Decimal Matrix Inversion
Use of Crout Method in floating-decimal notation in IBM Model I Card-Programmed Calculator.
Date:
April 1955
Creator:
Trantham, F. M., Jr.
System:
The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: November 1958-January 1959
Report documenting the ongoing research and developments of the Oak Ridge National Laboratory's Homogeneous Reactor Project.
Date:
April 16, 1959
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Spectra of Gamma Rays Produced by the INteraction of ~160-MeV Protons with Be, C, O, Al, Co, and Bi
Report concerning the production of gamma ray spectra of gamma rays by the interaction of ~160-MeV protons with beryllium, carbon, oxygen, Aluminum, carbon monoxide, and bismuth. This also includes descriptions of the apparatus used and a discussion of the results.
Date:
April 1965
Creator:
Zobel, W.; Maienschein, F. C. & Scroggs, R. J.
System:
The UNT Digital Library
Thorium-Uranium-233 Oxide (Kilorod) Facility : Rod Fabrication Process and Equipment
Report documenting "the design, construction, and operation of the Kilorod Facility and its fabrication equipment" (p. 42) as well as its economic viability.
Date:
April 1964
Creator:
Sease, J. D.; Lotts, A. L. & Davis, F. C.
System:
The UNT Digital Library
Some Major Fuel-Irradiation Test Facilities of the Oak Ridge National Laboratory
Report describing various reactors, six thermal conduction capsules, three loop facilities, miscellaneous equipment, and shop facilities maintained by the Oak Ridge National Laboratory.
Date:
April 1964
Creator:
Trauger, Donald B.
System:
The UNT Digital Library
An Elliptic Integral Computer Package for Magnetic Fields, Forces, and Mutual Inductances of Axisymmetric Systems, and a Versatile Line-Tracing Routine
Report describing a set of high-precision routines for the IBM 7090 that perform efficiently the calculations most often required on axially symmetric magnetic systems. The routines compute the vector potential, field components, and the mixed gradient for current systems and for certain idealized distributions of magnetized matter. The programs for the current systems were developed from a set of six equations in elliptic integrals, which suffice when correlations are fully exploited for all the relevant properties of loops and solenoids.
Date:
April 1965
Creator:
Garrett, M. W.
System:
The UNT Digital Library
Army Reactors Program Annual Progress Report: 1962
Report summarizing ongoing nuclear work performed by the ORNL for the United States Army.
Date:
April 10, 1963
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: December 1961
Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.
Date:
April 6, 1962
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Measurement of α, the Ratio of the Neutron Capture Cross Section to the Fission Cross Section, for ²³⁵U in the Energy Region from 3.25 eV to 1.8 keV
Report issued by the Oak Ridge National Laboratory discussing techniques to obtain measurements of alpha for enriched uranium. Descriptions of equipment and experiments used to obtain alpha are presented. This report includes tables, and illustrations.
Date:
April 1965
Creator:
deSaussure, G.; Weston, L. W.; Gwin, R.; Russell, J. E. & Hockenbury, R. W.
System:
The UNT Digital Library
Optical Mapping of Oak Ridge Research Reactor Experiment Tubes
Report issued by the Oak Ridge National Laboratory discussing optical mapping of experiment tubes. Descriptions of experiment equipment, and designs of the tubes are presented. This report includes tables, illustrations, and photographs.
Date:
April 1965
Creator:
Abbatiello, A. A.
System:
The UNT Digital Library
Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements
This report summarizes only that portion of the injection-casting experiments in which the castings were made with air pressure.
Date:
April 1961
Creator:
Koler, R. K.
System:
The UNT Digital Library
Quarterly Progress Report Research and Development Activities Fixation of Radioactive Residues: October - December, 1964
Report presenting research and development activities in the field of radioactive wastes. This particular report is concerned with the fixation of radioactive residues when the failure of a pot liner destroyed the furnace.
Date:
April 15, 1965
Creator:
Platt, A. M.
System:
The UNT Digital Library
The Purex process : a Solvent Extraction Reprocessing Method for Irradiated Uranium
Purex process which utilizes solvent extraction to separate and purify uranium and plutonium from each other and from fission products contained in irradiated uranium fuel elements.
Date:
April 8, 1957
Creator:
Irish, E. R. & Reas, W. H.
System:
The UNT Digital Library
An Automatic Monitor for As76 Concentrations in Reactor Cooling Water
Report that describes the development, design, and operation of a prototype instrument meant to monitor the As76 concentration in reactor cooling water streams.
Date:
April 1963
Creator:
Rieck, H. G. 1922-
System:
The UNT Digital Library
Beta-Gamma Dose Rates from U232 in U233
This report defines in detail the source of the dose rate of U233 and describes a method by which they may be predicted.
Date:
April 1964
Creator:
Owen, F. E.
System:
The UNT Digital Library
International Conference on Fundamental Aspects of Weak Interactions: Held at Brookhavan National Laboratory, September 9-11, 1963
Report issued by the Brookhaven National Laboratory discussing papers presented at the International Conference on Fundamental Aspects of Weak Interactions. Each paper that was presented at the conference is included. This report includes tables, illustrations, and photographs.
Date:
April 1964
Creator:
Brookhaven National Laboratory
System:
The UNT Digital Library
A Generalized Computer Program for Flowsheet Calculation and Process Data Reduction
Report issued by the Argonne National Laboratory discussing the PACER-65 computer program. As stated in the summary, the program "has been developed and utilized for flow sheet calculations and process-data reduction. PACER-65 is an executive program in which material- and energy-balance equations, conversion factors, etc., for each processing step are described by separate subroutines" (p. 5). This report includes tables, and illustrations.
Date:
April 1966
Creator:
Koppel, L. B.; Alfredson, P. G.; Anastasia, L. J.; Knudsen, I. E. & Vogel, G. J.
System:
The UNT Digital Library
Topic: a Fortran Program for Calculating Transport of Particles in Cylinders
Report discussing the use of TOPIC Sn computer code in the attempt to find a solution to the Boltzmann transport equation.
Date:
April 1964
Creator:
Putnam, G. E.
System:
The UNT Digital Library
A Study of the Feasibility of a Small Scale Reprocessing Plant for the Dresden Nuclear Power Station
Report describing the design, feasibility, and economic concerns of a small-scale reprocessing plant.
Date:
April 28, 1961
Creator:
Schneider, H.; Fletcher, R. D.; Codding, J. W.; Bearden, R. G.; Erickson, E. E.; Horn, S. J. et al.
System:
The UNT Digital Library
An Evaluation of Four Processes for Recovering Uranium from Zirconium Fuels at the Idaho Chemical Processing Plant
Report evaluating the technical and economic feasibility of four zirconium fuel processes: the present STR process, the modified Zirflex process, the barium fluozirconate process, and the sodium formate process.
Date:
April 27, 1962
Creator:
Burn, P.
System:
The UNT Digital Library