9-ANGIE : a Two-Dimensional, Multigroup, Neutron-Diffusion-Theory Reactor Code for the IBM 709 or 7090 (open access)

9-ANGIE : a Two-Dimensional, Multigroup, Neutron-Diffusion-Theory Reactor Code for the IBM 709 or 7090

The 9-ANGIE, one of a series of reactor neutronic programs for an IBM 709 or 7090 data processing system, solves the time-dependent, multi-group, neutron diffusion equation for one to eighteen energy groups applied to a rectangular mesh superimposed on either an x-y or an r-z plane. It is characterized by its generalities in region description, boundary conditions, etc., without sacrificing simplicity of input preparation and ease of machine operation. The notation, the style, and the format have been held as consistent as possible with 9-ZOOM, the companion one-dimensional program.
Date: October 28, 1960
Creator: Stone, Stuart P.
System: The UNT Digital Library
9-Zoom : A One-Dimensional, Multigroup, Neutron Diffusion Theory Reactor Code for the IBM 709 [Supplement] (open access)

9-Zoom : A One-Dimensional, Multigroup, Neutron Diffusion Theory Reactor Code for the IBM 709 [Supplement]

The following document describes the usage of the LRL 9-ZOOM code, a neutron diffusion theory reactor code for the IBM 709. The code has been modified to solve configuration of a series of stacked cylindrical disks, designating a new geometry case.
Date: July 12, 1960
Creator: Stone, S. P.
System: The UNT Digital Library
100-N Decontamination Facility Design Guide. (open access)

100-N Decontamination Facility Design Guide.

Space has been reserved near the southeast corner of the 100-N Area for the 122-N Decontamination Facility. Previous correspondence between Burns and Roe, Inc and General Electric bae discussed various facilities which might be needed in the building. The concepts of the decontamination processes are under active development by research groups at Hanford. At present, there are several workable processes known; each one has one or more fairly serious drawbacks.
Date: March 8, 1960
Creator: Bainard, W. D.
System: The UNT Digital Library
568 Report (open access)

568 Report

Final report for a grant contract documenting information about the scope of the project and results.
Date: 1960
Creator: Pollard, Ernest C. (Ernest Charles), 1906-1997
System: The UNT Digital Library
Accelerator Beam Pulsing System With Extremely Wide Range of Pulse Lengths and Pulse Repetition Rates (open access)

Accelerator Beam Pulsing System With Extremely Wide Range of Pulse Lengths and Pulse Repetition Rates

The following document describes the usage and results of sending pulsed beams of electrically charged particles with electrically wide range of pulse lengths and pulse repetition rates.
Date: June 28, 1960
Creator: Aaland, Kristian
System: The UNT Digital Library
Additional Miscellaneous Tools in the HRT Core (open access)

Additional Miscellaneous Tools in the HRT Core

This memorandum presents a description of several additional miscellaneous HRT core maintenance tools, not in an earlier report (1). These tools were used in the removal of the cut up diffuser plates, probing the core wall, gauging the size of the holes, and other simple tasks. Function, design, and operation are described for the following items.
Date: September 26, 1960
Creator: Holz, P. P.
System: The UNT Digital Library
Adsorption of Radioactive Gases on Activated Carbon (open access)

Adsorption of Radioactive Gases on Activated Carbon

The purpose of this experiment is to study the quantitative adsorption characteristics of a carbon adsorber bed receiving a radioactive inert gas in a helium stream. An objective of the experiment is to measure the equilibrium transmission of the radio-active gas through a carbon adsorber in order to determine if radio-active decay of the adsorbed gas permits additional adsorption.
Date: August 31, 1960
Creator: Madey, Richard; Barker, J. J.; Beebe, M. R. & Stephenson, T. E.
System: The UNT Digital Library
An Aerodynamic Raindrop Sorter. Technical Progress Report No. 1. (open access)

An Aerodynamic Raindrop Sorter. Technical Progress Report No. 1.

A pilot model of an Aerodynamic Raindrop Sorter was constructed along the lines suggested by mathematical analysis. The function of the analyzer is to sort natural rain according to drop size and to collect the sorted drops for further analysis. The pilot model, a small wind tunnel inclined at 45 deg to the horizontal, demonstrated the feasibility of aerodynamic rain drop sorting over a wide range of drop sizes. (auth)
Date: January 1960
Creator: Dingle, A. Nelson & Brock, Fred V.
System: The UNT Digital Library
[Aerosol Generator Design] : Letter Report (open access)

[Aerosol Generator Design] : Letter Report

The following report provides information on an aerosol generator fit to produce fine particles by a vaporization-condensation technique. Included is a diagram of the essential components of the generator.
Date: October 19, 1960
Creator: Rosinski, John & Stockham, John D.
System: The UNT Digital Library
After Shutdown Heating in the HFIR (open access)

After Shutdown Heating in the HFIR

After shutdown heating rates have been calculated for the target, control plates, and the beryllium reflector of the HFIR. Hilvety previously calculated the after shutdown heating rates in the element and his results are reported in ORNL CP-60-4-110. Decay times of 1.0 10, 10^2, 10^3, 10^4, and 10^5 seconds have been considered, and heat fluxes have been computed for all of the mentioned components. The greatest heat fluxes were found to be at the surfaces of the control plates and the permanent beryllium reflector.
Date: December 29, 1960
Creator: McLain, H. A.
System: The UNT Digital Library
An Algorithm for Construction Feasible Schedules and Computing Their Schedule Times (open access)

An Algorithm for Construction Feasible Schedules and Computing Their Schedule Times

"An algorithm for the generation of feasible schedules and the computation of the completion times of the job operations of feasible schedule is presented. Using this algorithm, the distribution of schedule times over the set of feasible schedule—or a subset of feasible schedules—was determined for technological orderings that could occur in a general machine shop. These distributions are found to be approximately normal. Biasing techniques corresponding to “first come first serve,” random choice of jobs ready at each machine and combinations of these two extremes were used to compute distributions of schedule times."
Date: November 15, 1960
Creator: Heller, Jack & Logemann, George
System: The UNT Digital Library
Aluminum Alloy Work at Hanford (open access)

Aluminum Alloy Work at Hanford

Investigation of aqueous and steam corrosion at elevated temperature has been carried on at Hanford for several tears. A number of reports have been published on various phases of the corrosion program but, except for monthly reports, little has been written on the progress of the Corrosion and Coatings Operation alloy development program. This interim report will outline the more important current phases of the aluminum alloy program.
Date: May 6, 1960
Creator: Bowen, H. C.
System: The UNT Digital Library
Analog and Digital Readout on an IBM Output Writer (open access)

Analog and Digital Readout on an IBM Output Writer

Abstract: A control system to provide digital printing and to plot an analog trace on an electric operated IBM model 11C Output Writer is described. The Digital mode of operation translates multidigit numbers through a set of commands to print each digit serially, then presents them to the output writer in a time sequence. The Analog mode of operation converts a d.c. input voltage to a digital number and by tab and space bar commands translates the carriage horizontally a distance proportional to this number.
Date: September 7, 1960
Creator: Graveson, R. T. (Robert T.)
System: The UNT Digital Library
Analog Computer Analysis of the Thermal Behavior of the EDCR Due to Reactivity Accidents (open access)

Analog Computer Analysis of the Thermal Behavior of the EDCR Due to Reactivity Accidents

The ORNL analog computer was used to examine one aspect of a safety system for the EGCR. The thermal behavior of the fuel as a result of increases in reactivity at various power levels and gas flows was examined. Safety actions initiated by wither a flux-minus-flow signal or a reactor outlet gas temperature signal were included in simulation.
Date: December 16, 1960
Creator: Pierce, R. M.
System: The UNT Digital Library
Analog Stimulation of HRP In-Pile Slurry Loop Facility in the LITR (open access)

Analog Stimulation of HRP In-Pile Slurry Loop Facility in the LITR

An analog simulation is made of the HRP in-pile slurry loop in the LITR. The radiolytic gas pressure in the pressurizer is determined. This pressure is a result of the generation of radiolytic gas in the loop core. A graphical result is obtained showing the effect of catalyst activity and pressurizer flow rate on the pressure rise from radiolytic gas. The thermal behavior of the system is studied, and the response to various controller settings is predicted. Controller settings very near optimum for the actual process were recommended from the analog study,
Date: November 28, 1960
Creator: Hinton, D. B.
System: The UNT Digital Library
Analog Study of the Reference Design of the Gas-Cooled ORR Loop No. 1 (open access)

Analog Study of the Reference Design of the Gas-Cooled ORR Loop No. 1

A stimulation study of the deign as of June 1960 of the gas-cooled ORR Loop No. 1 was made using the ORNL analog computer. The proposed method of temperature control is evaluated, and the dynamic behavior of the loop for accidents and component failures is presented in graphical form.
Date: November 8, 1960
Creator: Ball, S. J.
System: The UNT Digital Library
Analysis of Nucleon-Nucleon Scattering Experiments (open access)

Analysis of Nucleon-Nucleon Scattering Experiments

Presented at session S-1 of the Tenth Annual International Conference on High-Energy Physics, Rochester, New York, August 25- September 1, 1960. The analysis of the latest experiments on p-p scattering at 210 Mev makes it probable that there is a unique set of phase shifts at this energy. Under reasonable assumptions about continuity of the phase shifts and the behavior of the higher partial waves, it is possible to pick a unique solution also at 310 and 95 Mev. This opens a new era in the analysis of nucleon-nucleon scattering, which should lead to a unique model for the scattering matrix up to 400 Mev. Theoretical attempts to calculate a "meson potential" from field theory have not been successful, and the semi-phenomenological potential models, although now in good qualitative agreement with experiment, are not quantitatively reliable. Instead of using these models as a basis for an energy-dependent parameterization of the scattering matrix, as was done by Breit and his collaborators, it is here argued that the Mandelstam representation offers a more reliable starting point. A formalism is developed which allows the one and two pion exchange interaction to be included exactly and gives a Lorentz-invariant description of the rest of …
Date: August 1960
Creator: Noyes, H. Pierre.
System: The UNT Digital Library
Analysis of Six-Bar Linkage Using Digital Computer (open access)

Analysis of Six-Bar Linkage Using Digital Computer

Summary. The analysis of the motion of a six-bar linkage is difficult because of the large number of variables involved and the large number of calculations that have to be made for each position of the linkage. If a digital computer is used to make the calculations required for a multi-position analysis of a mechanism, it is feasible to design by analyzing a large numbers of similar linkages and selecting the optimum configuration. In this paper expressions have been derived for the output angle as a function of the input angle and the transmission angle as a function of the input angle for any single-degree-of-freedom six-bar linkage for which the parameters are known An example showing the usefulness of a six-bar computer program as a mechanism design tool is discussed.
Date: May 20, 1960
Creator: Dunk, A. C. & Hanson, C. L.
System: The UNT Digital Library
Analysis of the Moon's Surface by Nuclear Reactions (open access)

Analysis of the Moon's Surface by Nuclear Reactions

Introduction. With the imminence of non-destructive landings of small instrumented payloads on the moon, many suggestions are being put forth as to methods of analyzing its surface. It is the purpose of this report to present a body of information which, it is hoped, will be useful in examining the feasibility of an early nuclear experiment to determine the elemental constituents of the lunar surface. The reasons for considering a nuclear approach is that it may be possible to perform an analysis without complex and elaborate manipulations, sample preparation or rigid geometrical constraints. Only those experimental designs which come within the presently-available or very-near-future general boundary conditions on weights, power, vehicles, etc., are discussed. The general approach is to consider the bombardment of the lunar surface with various nuclear beams and to examine the possible nuclear reactions which are know to be dependent on the mass and charge of the irradiated material. Then, those resultant radiations are sought which can be detected with little-or-no loss or distortion of the information which they contain.
Date: April 1, 1960
Creator: Martina, E. F. & Schrader, Carlton D.
System: The UNT Digital Library
Analysis of Uranium Fuel-Element Wafers from Atomics International for Uranium, Plutonium and Samarium (open access)

Analysis of Uranium Fuel-Element Wafers from Atomics International for Uranium, Plutonium and Samarium

Five irradiated and five unirradiated wafers were analyzed. Each wafer was analyzed for samarium by emission spectrography. The unirradiated wafers were analyzed for uranium by coulometric and potentiometric methods and for uranium isotopes by mass spectrometry. The irradiated wafers were analyzed for uranium and plutonium by coulometric methods, for plutonium isotopes by the 256-channel alpha pulse analyzer, and for the isotopes of uranium and of plutonium by mass spectrometry. The methods of preparing wafers for analysis are discussed; the data are tabulated.
Date: December 27, 1960
Creator: Gaitanis, M. J.
System: The UNT Digital Library
Analysis of Zero Power Experiments on SM-1 Core II and SM-1A Core I (open access)

Analysis of Zero Power Experiments on SM-1 Core II and SM-1A Core I

Abstract: An analysis of SM-1 Core II and SM-1A Core I zero power experiments was made by comparing these cores to each other and to AM-1 Core I on the basis of critical bank positions, bank calibrations and available chemical analyses of the fuel plate compositions. The effects of replacing boron absorbers by europium absorbers upon rod worth and stuck rod conditions were studied. Comparisons of measured and calculated power distributions were made. It was concluded that both SM-1 Core II and SM-1A Core I contain nearly identical B-10 loading of 17.79 grams, compared to the best estimate of 15.75 grams for SM-1 Core I. The available data indicates that all three cores possess similar nuclear characteristics.
Date: October 5, 1960
Creator: Paluszkiewicz, S.
System: The UNT Digital Library
Anion Exchange of Neptunium in Nitrate Solutions (open access)

Anion Exchange of Neptunium in Nitrate Solutions

Technical report. From Abstract : "The absorption and elution of the anionic nitrate complex of neptunium (IV) were studied with several anion exchange resins and under a wide variety of conditions." From Introduction : "The objective of this study was to provide a technical basis for selecting process conditions for the recovery of Np."
Date: December 1960
Creator: Burney, Glenn A.
System: The UNT Digital Library
Anion Exchange Recovery of Plutonium From Reduction Residues (open access)

Anion Exchange Recovery of Plutonium From Reduction Residues

Technical report. From Abstract: "An anion exchange process was demonstrated for the recovery of plutonium from waste produced in the reduction of plutonium salts to the metal. Plutonium in a highly salted 6M nitric acid solution derived from the dissolution of slag and crucible waste was separated from impurities by absorbing the Pu (IV) nitrate complex on the anion exchange resin and subsequently eluting with nitric acid. A flowsheet for plant operation is presented."
Date: February 1960
Creator: Russell, Edwin R.
System: The UNT Digital Library
Annual Progress Report of Methods to Increase Burnout Heat Transfer (open access)

Annual Progress Report of Methods to Increase Burnout Heat Transfer

"Acoustic energy generated by mechanical or electrical signals and its effect on pool boiling of isopropanol were studied. Daring the course of the investigation, a method was devised to determine the amount of heat-transfer surface wetted by the boiling isopropanol. Plots of heat flux versus temperature difference for each frequency showed that the acoustic energy did not significantly affect the heat flux at burnout, but slightly increased the critical temperature difference. No general effect of frequency variation was found even at the frequencies of the "boiling songs" of isopropanol. The over- all effect of the acoustic energy was to disturb the vapor tending te coat the heat transfer surface. This was most evident from the absence of film boiling even at temperature differences far above the critical temperature difference. The application of alternating current to the boiling system gives promise of a self-regulating method to increase boiling heat transfer when required, and is the most significant new finding of this investigation. Two pertinent Russian papers were translated and are appended."
Date: September 30, 1960
Creator: Markels, Michael; Durfee, Robert L. & Richardson, Robert
System: The UNT Digital Library