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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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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 were made at horizontal distances from 250 to 1500 yards from the tower. Dose contributions from recoil protons H/sup 1/ (n, gamma )D/sup 2/ and N/sup 14/(n,p)C/sup 1 reactions are considered. (auth)
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). The present report is the second for the 15-minute Dingus area; a report by Adkison (1957) has been published for the White Oak quadrangle and a third report is in preparation for the Lenox quadrangle. Other published reports for quadrangles in the vicinity are those by Englund (1955) for Cannel City to the west; Bergin (1962) for Seitz to the southwest; and Hauser (1953) for Paintsville to the east.
Date: 1963
Creator: Adkison, W. L. & Johnston, J. E.
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 between the poison rings and the outer aluminum sheath, heat generation rate or reactor power level, the heat transfer contact coefficient between the rod and the graphite channel, and the cooling water temperature or cooling flow rate. For contact coefficients between 200 and 700 Btu/hr -- ft{sup 2} -- {degree}F and for diametral clearances around the poison of 5 mils to 20 mils, the maximum sheath temperature was calculated to vary between 350{degree}F and 650{degree}F. The dependence of sheath temperature upon the rod coolant temperature or coolant flow rate was found to be small enough to be neglected in the normal flow range of 12 gpm to 15 gpm. For a given increase of the average coolant temperature, the maximum sheath temperature increased about one half as much. Reversing the coolant flow in an HCR would not significantly reduce the maximum sheath temperature.
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 to be possible, and indeed desirable, to standardize the patterns into one front face coring pattern and one rear face coring pattern for all five of the reactors: B, D, F, DR, and H. The resulting coring patterns are presented. These coring patterns will significantly reduce the net rate of expansion in the filler blocks and consequently reduce the inlet and outlet humps in the process channels. This will allow standard 8-inch fuel elements to be charged in all tubes. The afore-mentioned coring patterns will limit the pile gas atmosphere to a range of between 90% He - 10% CO{sub 2} and 100% He. If a greater percentage of CO{sub 2} were used following the adoption of the coring patterns, the possibility of exceeding the maximum graphite temperature limit in the fringes would exist with reactor operation at the same or higher power level. It is recommended that the rear coring be done simultaneously with the front coring. Future reactor power level increases will not be restricted as a direct result of the proposed coring patterns. The primary effect will be to reduce the front-to-rear graphite temperature gradients. The present limitations to power level increases would still be the limiting conditions after the completion of the channel coring.
Date: June 20, 1963
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department
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Magnesium Turnover in Man

Description: Data are reviewed from a number of studies on the metabolism of Mg in man and the role of Mg in biological processes. Results are reported from studies using Mg/sup 28/ as a tracer of Mg metabolism in laboratory animals and in man in health and various disease states. It is postulated that the role of Mg in many vital processes may be explained by the fact that the Mg ion tends to form hydrates and double salts and hence has the capacity for complex formation. (C.H.)
Date: October 1963
Creator: Aikawa, Jerry K.
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 are described which attempt to assimilate the most drastic thermal transient that could occur in both units and to evaluate the effect of the resulting stresses on the Inconel overlay and the tube-to-tubesheet welds. (N.W.R.)
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 analysis to obtain the energy of the first neutron is presented. Comparison of the results of this analysis to angular-distribution studies suggests that each neutron removes 2 to 4 h units of angular momentum. The relation between the average total photon energy and the average angular momentum removed by photons is obtained. Comparison with the average photon energy from other work leads to an average of 1.8 plus or minus 0.6 h for the angular momentum removed by each photon. The excitation energy E/sub j/ of the lowest-lying state of spin J was estimated. (auth)
Date: January 1, 1963
Creator: Alexander, J.M. & Simonoff, G.N.
Partner: UNT Libraries Government Documents Department
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Differences in Personality Characteristics among Two Groups of Art Majors Varying in Creativity and a Control Group

Description: The present study is somewhat exploratory in nature in that it is interested in determining some of the factors which correlate with creativity. The study will limit itself to investigating the factors measured by Cattell's Sixteen Personality Factor Questionnaire as they relate to creativity among high and low Creative art majors and non-art majors. To this end, it is hypothesized that a difference will be found among the mean scores of the three groups for at least thirteen of the sixteen factors.
Date: August 1963
Creator: Allred, Raymond Coye, 1930-
Partner: UNT Libraries
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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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Space Vehicle Shielding Studies Calculations of the Attenuation of a Model Solar Flare and Monoenergetic Proton Beams by Aluminum Shields

Description: Using the straight-ahead approximation, nucleon-meson cascade calculations have been carried out for a typical proton flare spectrum incident on a shield and for approximately monoenergetic incident proton beams. The shield material considered has approximately the properties of Al. The results from the monoenergetic beams may be used to obtain shielding information for any incident proton spectrum. (auth)
Date: January 23, 1963
Creator: Alsmiller, R. G., Jr. & Murphy, J. E.
Partner: UNT Libraries Government Documents Department
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Nucleon-Meson Cascade Calculations: Transverse Shielding for a 45-Gev Electron Accelerator. Part Ii

Description: In a previous report nucleon-meson cascade calculations were carried out for several cases of interest in the design of the transverse shield for the proposed 45-Bev linear electron accelerator at Starford University. In this report results are given for several additional cases. Muon, neutron, pion, and proton intensities as function of energy and distance for varying angles are given. Corresponding doses are also included. (D.C.W.)
Date: February 28, 1963
Creator: Alsmiller, R. G., Jr.; Alsmiller, F. S. & Murphy, J. E.
Partner: UNT Libraries Government Documents Department
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