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Economic Evaluation of a 300 Mwe Fast Supercritical Pressure Power Reactor

Description: Report regarding Hanford Laboratories' 300 Mwe fast supercritical pressure power reactor. This includes descriptions of the plant and reactor, their operations, safety systems, and plant economics. Appendices begin on page 107.
Date: December 9, 1963
Creator: Aase, D. T.; Fox, J. C.; Hennig, R. J.; Peterson, R. E.; Stewart, S. L. & Toyoda, K. G.
Partner: UNT Libraries Government Documents Department
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MERCURY PUMP DEGRADATION.

Description: No Description Available.
Date: January 1, 1963
Creator: Abramson, P.B.
Partner: UNT Libraries Government Documents Department
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NEUTRON TISSUE DOSE AT LARGE DISTANCES FROM AN ELEVATED UNSHIELDED REACTOR

Description: The neutron tissue dose at large distances from a fission source was studied by using a water-filled phantom and four different detectors: a BF/sub 3/ counter, a polyethylenelined ethylene-filled proportional counter, indium foils, and nuclear emulsions. The source of fission neutrons was the ORNL Health Physics Research Reactor which was attached to a hoist which was in turn installed on a 1530-foot tower. The reactor could be operated at any elevation from 27 to 1500 ft. The phantom studies w… more
Date: March 11, 1963
Creator: Aceto, H. Jr.; Pick, M.A. & Stephens, L.D.
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report: April 1963

Description: Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during April 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: May 15, 1963
Creator: Adams, R. M. & Glassner, A.
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report: March 1963

Description: Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during March 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: April 15, 1963
Creator: Adams, R. M. & Glassner, A.
Partner: UNT Libraries Government Documents Department
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Geology and Coal Resources of the Salyersville North Quadrangle, Magoffin, Morgan, and Johnson Counties, Kentucky

Description: From introduction: The U.S. Geological Survey has conducted investigations of the geology and coal resources of the area in and adjacent to the Salyers-ville North quadrangle in the Eastern Kentucky coal field (fig. 7). The Salyersville North quadrangle lies between lat. 3745' and 37052'30'' N., and long. 8300' and 83 07'30'' E.; it is a 71/2-minute quadrangle in the southeast quarter of the Dingus 15-minute area which also includes the Dingus, Lenox, and White Oak 7 -minute quadrangles (fig. 8… more
Date: 1963
Creator: Adkison, W. L. & Johnston, J. E.
Partner: UNT Libraries Government Documents Department
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Polymerization in Solid Solutions of Acrylamide in Propionamide

Description: It has previously been shown that the polymer formed in solid state polymerization of acrylamide is amorphous in spite of the fact that the reaction takes place within a crystalline solid. The stage at which it becomes amorphous is not known at present. Work with dilute solid solutions of acrylamide in propionamide suggests that this occurs after the addition of, at most, a very few monomer units.
Date: March 26, 1963
Creator: Adler, G. & Reams, W.
Partner: UNT Libraries Government Documents Department
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High Dilution On-Stream Isotopic Tracers Annual Report: 1962

Description: Introduction: The general aims of this work were to further the practical applications of radioisotope technology.
Date: 1963?
Creator: Aebersold, Paul C. & Bizzell, Oscar M.
Partner: UNT Libraries Government Documents Department
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The Mechanism of Desalination by Reverse Osmosis

Description: Report describing the various parameters operative in fabricating desalination membranes for the Reverse Osmosis Process and the mechanism of separation. The bulk of the membrane contains huge quantities of capillary water which permits the movement of water through the body of the membranes at extremely rapid rates, there being essentially no pressure drop in this portion of the membrane.
Date: 1963
Creator: Aerojet-General Corporation
Partner: UNT Libraries Government Documents Department
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Old pile HCR operating temperatures

Description: A study was made to determine operating temperatures of old pile HCR sheaths. The calculations were performed with the aid of a FORTRAN coded program for the IBM 7090. The difficulty of determining the correct value for the contact coefficient between the HCR and the graphite channel at any point in the channel length resulted in performing the calculations in a parametric style. The independent system parameters were varied during the calculations. These parameters are diametral spacing betwee… more
Date: October 10, 1963
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department
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Proposed graphite coring patterns for B, D, F, DR, and H Reactors

Description: Heat transfer calculations were performed with the aid of the IBM 7090 to determine whether or not feasible graphite channel coring patterns could be adopted at the five older Hanford Reactors. The purpose of front and rear process channel coring is to significantly reduce or eliminate net expansion of the fringe graphite by raising the operating temperature above the annealing temperature of 300{degree}C. The results of the study show that such coring patterns are possible. Also, it was found … more
Date: June 20, 1963
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department
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Separation of Beryllium from Fission Products in a Nitrate Medium - Preliminary Experiments Using Solvent Extraction

Description: Preliminary experiments using acetylacetone in the presence of ethylenediaminetetraacetic acid to separate major quantities of beryllium from fission products are reported. Using 2M beryllium solutions, decontamination factors of the order of 10/sup 3/ were obtained with trace quantities of the more important fission products. This is sufficiently encouraging for the work to be repeated at higher activity levels.
Date: March 1963
Creator: Aggett, J
Partner: UNT Libraries Government Documents Department
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Final report: PITA-18 use of nonpoisonous splines for longitudinal flux traversing

Description: Optimization of the reactor process involves the knowledge of the longitudinal flux distribution on a semicontinuous, routine basis. The nonpoisonous spline was proposed as a way for obtaining flux traverses at any time during reactor operation, in virtually any location in the core. This report summarizes the findings of a feasibility study conducted in conjunction with PITA-18 and thus serves as a termination of the test phase of spline traversing.
Date: May 1, 1963
Creator: Albertson, D. G. & Bowers, C. E.
Partner: UNT Libraries Government Documents Department
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Tube-To-Tubesheet Welding Development Programs to 30 Megawatt Prototype Sodium Intermediate heat Exchanger and Steam Generator

Description: Special welding techniques for joining Inconel weld overlays on type 316 stainless steel tubesheets and channels are described. The program for the development of the required welding procedures are divided into three specific programs: overlaying Inconel filler Metal 82 on type 316 stainless steel, welding type 316 stainless steel tubes to a type 316 stainless steel tubesheet, and welding Inconel-type 316 stainless steel composite tubes to Inconel weld overlaid type 316 tubesheets. Shock tests… more
Date: 1963
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
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THE AVERAGE ENERGY AND ANGULAR MOMENTUM REMOVED FROM Dy COMPOUND NUCLEI BY NEUTRONS AND PHOTONS

Description: Excitation functions are presented for many heavy-ioninduced (HI) reactions that produce Dy/sup 149/, Dy/sup 150/, and Dy/sup 151/. Projectiles were C/sup 12/, N/sup 14/, N/sup 16/, O/sup 16, O/sup 18/, F/sup 1 9/, and Ne/sup 20/ of 4 to 10.4 Mev per amu. The reactions studied are all of the type (HI,xn), where x ranges from 3 to 9. A large fraction of the total reaction cross section is accounted for by these (HI,xn) reactions --9/10 at approximately 45 Mev to 1/2 at approximately 105 Mev. An … more
Date: January 1, 1963
Creator: Alexander, John M. & Simonoff, Gabriel N.
Partner: UNT Libraries Government Documents Department
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Solvent Extraction Processes for the Recovery and Separation of Uranium and Thorium - a Literature Survey

Description: A summary of the available literature on the development of the various processes for the separation of uranium and thorium from aqueous nitrate solutions is presented. Flowsheets are given corresponding to the various stages in the development of the Thorex processes.
Date: August 1963
Creator: Alfredson, Peter George & Farrell, M. S.
Partner: UNT Libraries Government Documents Department
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Neutron Diffraction Studies at the Puerto Rico Nuclear Center

Description: A neutron diffraction program was initiated recently at the Puerto Rico Nuclear Center. The two double crystal spectrometers in use were assembled with the aid of staff members of the Brookhaven National Laboratory. The first research problem to be completed was a single crystal structure analysis of CaWO4. Choosing the origin at the 4(a) tungsten site in the tetragonal I41/a cell. the 16(f) oxygen parameters were found to be as follows: x=0.2413 ± 0.0005, y=0.1511 ± 0.0006, z=0.0861 ± 0.0001.… more
Date: October 15, 1963
Creator: Almodovar, I; Bielen, H. J. & Frazer, B. C.
Partner: UNT Libraries Government Documents Department
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A Perturbation Method for Solving the Angle Dependent Nucleon-Meson Cascade Equations

Description: A method is described for obtaining an approximate solution to the equations describing a nucleon-meson cascade by using the angular dependence of the secondary particle production kernels as a perturbation. The usefulness of the method lies in the fact that in a slab geometry the equations that must be solved numerically are essentially the same as those that are used in the straight-ahead approximation and have been solved previously. (auth)
Date: July 30, 1963
Creator: Alsmiller, R. G., Jr. & Alsmiller, F. S.
Partner: UNT Libraries Government Documents Department
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Nucleon-Meson Cascade Calculations: Shielding Against an 800-Mev Proton Beam

Description: Nucleon-meson cascade calculations were carried out and the dose as a function of depth was obtained for an 800-Mev proton beam incident on a shield. The physical properties used for the shielding medium are only a rough approximation to the properties of any particular medium. Muon, neutron, pion, and proton dose rates and fluxes are listed. (auth)
Date: February 21, 1963
Creator: Alsmiller, R. G., Jr. & Murphy, J. E.
Partner: UNT Libraries Government Documents Department
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Nucleon-Meson Cascade Calculations: The Star Density Produced by a 24-Gev Proton Beam in Heavy Concrete

Description: The nuclear star density produced by a 24-Bev proton beam in a material having approximately the properties of heavy concrete is calculated. A comparison is made with experimental measurements made at CERN; but, since the quantity that can be calculated is not the same as that measured, no firm conclusions can be drawn. Proton, neutron, pion, and muon intensities are plotted vs. distance as are star densities. (auth)
Date: January 21, 1963
Creator: Alsmiller, R. G., Jr. & Murphy, J. E.
Partner: UNT Libraries Government Documents Department
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