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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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Multipurpose scintillation camera

Description: The scintillation camera is a nonscanning instrument for displaying the distribution of radioactive isotopes. It can be used, for example, to show abnormalities in the thyroid gland with I-131, the size, shape and location of kidneys with Hg-203 Neohydrin or to locate brain tumors either with Hg-203 Neohydrin or with the new positron emitting agent, Ga-68 EDTA. For many applications, the scintillation camera has higher sensitivity than conventional isotope scanners, and will produce pictures in less time or with a smaller quantity of isotope present. Alternatively, it produces better pictures if the conventional dosage and exposure factors are retained. Because of the short exposure time, and because the scintillation camera is continuously sensitive to all areas within its field of view, it is well adapted to taking rapid sequences of still pictures or time-lapse motion pictures of subjects in which the distribution of radioactivity is changing. For example, time lapse pictures have been taken showing I-131 Rose Bengal Bengal being excreted from the liver of children with liver disease and of I-131 hippuran going through the kidneys of patients suspected of kidney disease.
Date: July 1, 1963
Creator: Anger, H.O.
Partner: UNT Libraries Government Documents Department
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TABLES OF OXYGEN PRESSURES CALCULATED FROM THE HYDROGEN-WATER SYSTEM AND FROM THE DISSOCIATION OF CUPRIC OXIDE

Description: The dissociation of various mixtures of hydrogen and water vapor and of cupric oxide was calculated over a wide range of temperatures (from 600 to 1700 deg C for the H/sub 2/--H/sub 2/O system, and from 200 to 1000 deg C for CuO). The resulting partial pressures of oxygen are presented in tabular form. (auth)
Date: July 1, 1963
Creator: Atlas, L. M. & Moser, J. B.
Partner: UNT Libraries Government Documents Department
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PROCESSING OF MULTI-CHANNEL-ANALYZER NUCLEAR REACTION SPECTRA WITH THE NEWDAC PROGRAM

Description: A FORTRAN program is presented for processing pulse-height data for particles emitted from a nuclear reaction. The program corrects the particle energy for any absorber preceding the detector and computes the differential center-of-mass cross section as a function of the reaction Q value and the excitation energy of the final nucleus. The energies can be computed either relativistically or nonrelativistically. The program is written as a series of subroutines to facilitate possible expansion of the program and to allow easy accommodation of different data input routines. The output of the program is printed in tabular form and, at the discretion of the user, punched on cards for off-line plotting or for input to other programs. (auth)
Date: July 16, 1963
Creator: Ball, J.B.
Partner: UNT Libraries Government Documents Department
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A Survey of the Corrosion of Martensitic and Ferritic Stainless Steels in Pressurized Water

Description: >The corrosion resistance of mantensitic and ferritic austenitic stainless steels and carbon steels in pressurized water at 500 to 600 deg F is compared. Included are specific out-of-pile data for austenitic stainless steels, AISI types types 410, 420, 431, and 440C; the ferritic AISI types 430, 442, and 446; the precipitation-hardening type 17-4PH; and carbon steels, ASTM 212 A and B. Available corrosion results obtained under irradiation at exposures in the range of 7 x 10/sup 16/ to 3 x 10/sup 19/ nvt are also included for types 304, types of martensitic and ferritic stainless steels which were evaluated do not contain nickel. For application where it is desirable to minimize Co/sup 58/ activity produced from nickel, selection of a martensitic or ferritic stainless steel may be more appropriate than choosing the more popular nickel-bearing austenitic stainless steel or a fuel-element cladding material. Interpretation of the data indicates that, on the average, martensitic and ferritic stainless steels corrode more rapidly than austenitic alloys but more slowly than carbon and low-alloy steels. Under selected controlled water conditions or under irradiation, the corrosion of the nickel-free stainless steels appears to differ little from the austenitics. The corrosion of martensitic and ferritic stainless steels in pressurized-water systems therefore does not appear of such magnitude as to rule out development of these materials as the cladding fuel elements for specific applications. (auth)
Date: July 16, 1963
Creator: Beaver, R. J. & Leitten, C. F. Jr.
Partner: UNT Libraries Government Documents Department
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Final Report : Large Reactor Study for Sea Water Distillation

Description: From introduction: This report presents the results of a study of large nuclear reactor systems for supplying energy for the distillation of sea water.
Date: July 1963
Creator: Bechtel Corporation
Partner: UNT Libraries Government Documents Department
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Engineering Features of DCX-2

Description: The DCX-2 is a large, complex experimental apparatus. Its aim is the generation of a hot, dense plasma by the injection and dissociation of 600-kev hydrogen molecNoneular ions in a magnetic-mirror field. For facilitating this process, the molecular ions are given a long path in the machine, and the ion- pumping action of the plasma is used to maintain the vacuum. The major component systems of the apparatus are the ion source and accelerator, highvoltage power supply, magnet system, beam-injection duct, vacuum system, and dissociating arc. The design, construction, and performance of each component system, the constructional features not peculiar to any one component, and the instruments and techniques available for plasma study are described. (auth)
Date: July 26, 1963
Creator: Bell, P. R.; Culver, J. S.; DeCamp, S. M.; Ezell, J. C.; Kelley, G. G.; Lazar, N. H. et al.
Partner: UNT Libraries Government Documents Department
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A Review of Ultrasonic Imaging Methods, With a Selected, Annotated Bibliography

Description: This review includes a discussion of many methods for detecting ultrasonic images with emphasis upon the problems involved in a nondestructive inspection system employing ultrasonic imaging techniques. The detection methods are compared from the standpoint of threshold sensitivity. It is concluded that a system which will respond to an ultrasonic intensity of 10/sup -3/ w/cm/sup 2/ or less will probably be necessary for a practical nondestructive inspection system. The detection methods which meet this requirement include those classified as optical and mechanical, and as electronic. The annotated bibliography includes 74 entries, many of which contain more than one reference. Included in this bibliography are references to most of the known methods for ultrasonic imaging. (auth)
Date: July 1, 1963
Creator: Berger, H. & Dickens, R.E.
Partner: UNT Libraries Government Documents Department
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Pathfinder Atomic Power Plant. End Closure Development for Low Enrichment Superheater Fuel Rods

Description: Research on a welding process for closing the ends of pathfinder fuel elements is reported. Optimum parameters for certain variables (amperage, weld travel, preheat, etc.) affecting weld quality were determined, and two modified end cap designs were investigated and found to reduce weld sensitivity to certain variables. Use of chills on the fuel tube greatly improved weld puddie geometry and microstructure. Optimum weld parameters for rods containing UO/sub 2/ fuel were experimentally established. (D.C.W.)
Date: July 30, 1963
Creator: Boschke, R. A. & Wiggins, R. J.
Partner: UNT Libraries Government Documents Department
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Analog Computer B-5 Tests

Description: This report is an explanation of the response characteristics, some typical curves of displacements, velocities, etc., and the computer circuit diagram.
Date: July 11, 1963
Creator: Burack, R. D. & Maguire, A. F.
Partner: UNT Libraries Government Documents Department
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Statistical Treatment of Hot Channel Factors for Compact Reactors

Description: The theoretical development, statistical treatment, and application of hot channel factors in compact SNAP reactors as represented by the SNAP 8 experimental core loading are presented. The channel and rod power effects of variation in the concentrations of uranium, hydrogen, and poison in the fuel rods are given. The statistical distributions of all variables are examined. A random selection of rods and channels is compared to the actual SNAP 8 configuration, with no difference noted. Confidence limits are set on hot rod and hot channel factors. Various other factors and aspects of the problem are discussed. The results of the study showed that the hot channel factors may be reduced to less than +2% over the nominal power, as opposed to a hot channel factor of about +10% as previously determined by empirical methods. (auth)
Date: July 15, 1963
Creator: Cohn, P. D. & Evans, H. A.
Partner: UNT Libraries Government Documents Department
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Materials for Superheated Fuel Sheaths: Relative Performance of Alloys in Superheated Steam Environments

Description: From abstract: "Study of radiation effects upon the tensile properties of the alloys, corrosion behavior in the absence and presence of stress, effect of prolonged, high temperature exposures upon structure sensitive properties of the alloys, and physical metallurgical changes as a function of exposure in a superheat environment.
Date: July 1963
Creator: Comprelli, F. A.; MacMillan, D. F. & Spalaris, C. N.
Partner: UNT Libraries Government Documents Department
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Calculations on close-coupled processing for Pu-238 recovery

Description: Irradiation of Np-237 in Hanford reactors and recovery of the Pu-238 product in a close-coupled separations plant is currently of interest. Such a concept has the potential of increasing in Pu-238 production rates. The results of initial calculations on the subject are presented herein to aid further study and evaluation. Much of the information is presented in terms of the aqueous target system proposed in earlier work (i.e., irradiation and processing of an aqueous neptunium solution). However, most of the information can be converted for evaluation of a solid target system.
Date: July 10, 1963
Creator: Coppinger, E. A.
Partner: UNT Libraries Government Documents Department
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A STUDY OF THE POLYMERIZATION, DEPOLYMERIZATION, AND PRECIPITATION OF TETRAVALENT PLUTONIUM AS FUNCTIONS OF TEMPERATURE AND ACIDITY BY SPECTROPHOTOMETRIC METHODS: PRELIMINARY REPORT

Description: Studies were made on the kinetics of the polymerization of tetravalent Pu, depolymerization of polymeric Pu(IV), and properties of Pu(IV) poiymer under representative solution conditions of acidity, temperature, and ion concentrations encountered in fuel processing. The polymerization of tetravalent Pu was studied as a function of the Pu concentration, (1 to 8 mg Pu/ml), nitric acid concentration, (0.03 to 0.3 M), and temperature (25 to 95 deg ). Under these conditions, disproportionation and nitrate oxidation of the tetravalent Pu occurred and were also studied. It is clearly indicated that colloidal polymer formation is favored by an increase in the Pu concentration and temperature, or by a decrease in the acidity. Temperature had a pronounced effect on the rate and extent of polymer formation at any particular acidity. The effects of UO/sub 2/(NO/sub 3/)/sub 2/, Al(NO/sub 3/)/sub 3/, NaNO/sub 3/, and F/sup -/ upon the kinetics of polymer formation in acidic nltrate media were also determined at low acidities and elevated temperatures. In the presence of high concentrations of the nitrate salts the colloidal Pu(IV) polymer was observed to precipitate. The precipitation of aged colloidal Pu(IV) polymer by nitratecontaining electrolytes, HNO/sub 3/, Al(NO/sub 3/)/sub 3/, NaNO/sub 3/, and LiNO /sub 3/, was studied at 25 deg C. The Pu(IV) polymer was aged by refluxing for 24 hr at the boiling temperature. The amount of aged polymer precipitated reached a maximum at 2 to 3 M nitrate, and decreased thereafter with an increase in nitrate concentration. Precipitation did not occur above a nitrate concentration of 4 M. The depolymerization reaction kinetics of freshly prepared Pu(IV) polymer at fixed acidity were observed to be first order, depending only upon the concentration of Pu present as polymer. The results show that polymer formation and precipitation can be prevented by the proper control of solution …
Date: July 1, 1963
Creator: Costanzo, D A & Biggers, R E
Partner: UNT Libraries Government Documents Department
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NUCLEAR START-UP OF THE SPERT IV REACTOR

Description: The Spert IV facility, the initial critical experiment, the initial core, the operational core loading, and core parameter measurements (void and temperature coefficients, control rod worth, neutron flux distributions, etc.) made before initiation of the kinetics testing program are described. (auth)
Date: July 1, 1963
Creator: Crocker, J.G.; Koch, J.E.; Martinson, Z.R.; McGlinsky, A.M. & Stephan, L.A.
Partner: UNT Libraries Government Documents Department
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Water Spectra and Energy Exchange Kernels

Description: Many measurement of neutron spectra have been made in water assemblies. In these system a large part of the spectrum is given by an essentially Maxwellian distribution at the moderator temperature which is insensitive to the scattering model. Hence, the test of the energy exchange scattering kernel is in the difference of the spectrum and the fundamental or Maxwellian component. The figure shows the spectrum for the Nelkin model. Once the fundamental has been subtracted neither theoretical model seems to fit the data extremely well. Below kT the Nelkin model is a closer fit than the gas model but it underestimates the deviation from the Maxwellian whereas in the joining region it overestimates the distortion.
Date: July 11, 1963
Creator: Daitch, Paul B. (Paul Bernard), 1925- & Ohanian, M. J.
Partner: UNT Libraries Government Documents Department
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Development Test IP-556-D, supplement A, irradiation service request HAPO-278 outgassing rate of tritium at high temperature

Description: The nuclear heat generation rate in the first capsule irradiated was higher by a factor of two than was calculated. The original capsule was irradiated in a dry bore with cooling water in the annulus only. The new capsule will be irradiated in a water-cooled bore facility with additional cooling coils around the lithium containing tube. This will keep the inner capsule temperature below 150 C during the initial tritium buildup period prior to outgassing. This Supplement authorizes the irradiation of an additional capsule and the removal of the present facility and installation of a single tube general purpose facility. All remaining provisions of the original development test are in force except for minor exceptions due to the water flow in the bore which have been changed in the following writeup.
Date: July 5, 1963
Creator: DeMers, A. E.
Partner: UNT Libraries Government Documents Department
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A 23-Group Neutron Thermalization Cross Section Library

Description: A set of 23-group neutron cross sections for use in the calculation of neutron thermalization and thermal neutron spectral effects in SNAP reactors is compiled. The sources and methods used to obtain the cross sections are described. (auth)
Date: July 15, 1963
Creator: Doctor, R. D. & Boling, M. A.
Partner: UNT Libraries Government Documents Department
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Regional Hydrology of a Part of Southern Nevada: a Reconnaissance

Description: From introduction: This report summarizes the available hydrologic information for a part of Nevada surrounding the Nevada Test Site. It emphasizes the possibility that ground water may move from one basin to another, whereas the usual concept heretofore has been that the ground water of the region generally occurs in basins that are closed or nearly closed.
Date: July 1963
Creator: Eakin, Thomas E.; Schoff, Stuart L. & Cohen, Philip
Partner: UNT Libraries Government Documents Department
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NRX-B Module Bending Analysis

Description: A description is presented of a preliminary bending analysis of three module configurations designed for the 19-hole Kiwi-B4-type fuel element.
Date: July 29, 1963
Creator: Eggers, A.
Partner: UNT Libraries Government Documents Department
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