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Chemical Technology Division Unit Operations Section Monthly Progress Report, September 1961

Description: Nine samples of ThO/sub 2/ -UO/sub 2/ prepared as part of the solgel process development studies showed no consistent effects from small variations in several process parameters. The reaction of methane and copper oxide was studied. Engineering studies of the continuous dissolution of simulated U-Zr-Sn fuels in 6.5 M NH4F, 0.6-1.0 M NH/sub 4/NO/sub 3/, 0.1 M H/sub 2/O/sub 2/ were continued in modified 6-in.-dia. equipment. A total of 1642 kg of U from NaK bonded SRE Core I fuel rods wad dejacke… more
Date: April 1, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Partner: UNT Libraries Government Documents Department
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Murgatroyd-an Ibm 7090 Program for the Analysis of the Kinetics of the Msre

Description: The IBM 7090 program Murgatroyd is a revised and extended version of the IBM 704 program PET-I, which solves (by a fifth-order Runge-Kutta procedure) the coupled firstorder differential equations for power, delayed neutron concentration, and temperature in a one-region reactor as a function of time, given an input reactivity variation represented by a series of linear ramps. The basic extensions were those which were necessary to include the effects of the separate heat capacities and temperatu… more
Date: April 1, 1962
Creator: Nestor, C. W. Jr.
Partner: UNT Libraries Government Documents Department
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Measurement of Xenon Poisoning in the HRT

Description: Measurements obtained during three periods of HRT operations indicated that the xenon poison fraction was approximately 0.010. The technique used was based on mass spectrographic analyses of the stable xenon isotopes in the reactor off-gas stream. Models proposed to explain the measurements show that xenon, which is formed primarily by decay of iodine adsorbed on the pipe walls, is held up on the walls, out of the circulating stream, for an average period of about eight hours. (auth)
Date: April 19, 1962
Creator: Burch, W.D.
Partner: UNT Libraries Government Documents Department
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The Measurement of Energy and Intensity of Gamma Rays by Use of a Scintillation Spectrometer

Description: The analysis of gamma-ray spectra measured with a scintillation counter with an anticoincidence annulus is described in detail. In particular the problem of the determination of the energy and intensity of gamma rays from such measurements is considered. The shapes of the full-energy peaks in observed complex spectra are studied and an attempt is made to justify their description in terms of a Gaussian response function. The details of the statistical analysis of complex gamma-ray spectra are g… more
Date: April 1, 1962
Creator: Julke, R. T.; Monahan, J. E.; Raboy, S. & Trail, C. C.
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report, March 1962

Description: ABS>Developmental work is reported on the EBWR and Borax-V other general development work is reported in the area of liquid metal cooled reactors and particularly on the EBR-I and H, and the fast reactor test facility. General reactor technological development is described on applied reactor physics, reactor fuels development, reactor materials development, heat engineering and fluid flow, chemical separations, advanced systems, and nuclear safety. (J.R.D.)
Date: April 15, 1962
Partner: UNT Libraries Government Documents Department
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Crystallographic D-Space Computer Program

Description: D-Space is a computer program which generates indices (hld), tests for space-group extinctions, and calculates d,'' 1/d/sup 2/, sin theta , sin/sup 2/ theta , sin theta / lambda , sin/sub 2/ theta / lambda /sup 2/, theta , and 2 theta for any crystal system and space group, requiring only the unit cell constants as data input. Optional calculations are the single-crystal angle settings, phi and chi, and various Lorentz and Lorentz-polarization corrections. (auth)
Date: April 1962
Creator: Mueller, M. H.; Meyer, E. F. H. & Simonsen, S. H.
Partner: UNT Libraries Government Documents Department
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Radiation Problems Associated With the Handling of the Actinide Elements

Description: The hazards connected with the handling of actinide elements are surveyed. Emphasis is placed on Th, U, Np, and Pu. It is pointed out that the chemical toxicity of the actinides is usually minor when compared with radiochemi cal toxicity. Inhalation and ingestion are the important routes of entry but direct injection into the blood stream through wounds also requires consideration. Special enclosures, such as glove boxes, function primarily to minimize the risk of inhalation and aid in confinem… more
Date: April 1, 1962
Creator: Steindler, M.J.
Partner: UNT Libraries Government Documents Department
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A FORTRAN Program for Calculating Single Crystal Absorption Corrections

Description: A Fortran program is described for calculating the absorption correction for application to single crystal x ray or neutron intensity measurements. The program is available in the form of symbolic punched cards. InstrucPions are included. (J.R.D.)
Date: April 1, 1962
Creator: Wehe, D. J.; Busing, W. R. & Levy, H. A.
Partner: UNT Libraries Government Documents Department
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RADIOISOTOPES AND RADIATION APPLICATIONS. Quarterly Progress Report No. 12

Description: Continued research is reported in the areas of intrinsic radioactive tracers for industrial process control and the effects of structural factors on radioinduced graft polymerization. The use of Be-- Po neutron sources for production of short-lived isotopes is being investigated. Data are included on the effects of target volume, high-Z scattering media, target-isotope concentration, and macroscopic cross-section on speciflc and total activation produced with a 10-curie source. Research on graf… more
Date: April 18, 1962
Creator: Sunderman, D.N. ed.
Partner: UNT Libraries Government Documents Department
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Stress and Deflection of Boiler Fuel Element Boxes

Description: Equations were derived by strain-energy methods for analyzing the stress and deflection in the boiler fuel element boxes used in the Pathfinder nuclear reactor. These boxes are of two types, both constructed of Zircaloy lI. One box is approximately 5 in. sq. The second is approximately 10 1/2 in. sq divided internally into four compartments (5 in. sq) by a cruciform control-rod guide structure. Stress and deflection in the box walls are caused by pressure differences across the walls. The equat… more
Date: April 13, 1962
Creator: Vlies, L. E.
Partner: UNT Libraries Government Documents Department
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NEUTRON THERMALIZATION MEASUREMENTS USING AN ELECTRON LINEAR ACCELERATOR

Description: Discussions are presented concerning integral experiments primarily on water and graphite systems. A description of experimental facilities is included along with details of die-away experiments, infinite-medium spectrum measurements, spatially dependent spectrum measurements, spectrum measurements for graphite systems, and development of a subcritical assembly program. (J.R.D.)
Date: April 10, 1962
Creator: Beyster, J R
Partner: UNT Libraries Government Documents Department
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A STUDY OF THE SHIELD OF THE UNIVERSITY OF ILLINOIS TRIGA MARK II RESEARCH REACTOR

Description: Detailed measurements were made of the fast-neutron and gamma dose rates and the thermal-neutron fluxes existing at the surfaces of the biological shield of the University of Illinois TRIGA Mark II Research Reactor. Dose rates and fluxes were found to be extremely low. A comparison was made by means of threshold foil techniques between the fast-neutron flux in a beam hole of the reactor during steady-state operation at 1 kw and during a nominal 250 Mw, 30 msec pulse produced by rapid insertion … more
Date: April 23, 1962
Creator: Blosser, T.V.; Freestone, R.M. Jr. & Miller, J.M.
Partner: UNT Libraries Government Documents Department
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A PINHOLE CAMERA AUTORADIOGRAPHIC TECHNIQUE FOR ENCAPSULATED IRRADIATED FUEL SPECIMENS

Description: A gamma pinhole camera was devised to permit a nondestructive examination of irradiated specimens while still in sealed capsules. The camera was designed such that a complete experiment may be withdrawn from an irradiation facility, the specimen autoradiographed, and the experiment then reinserted if so desired. The pinhole aperture is 0.020 in., and the source to pinhole block is 4 ft. The image-to-source sizes are a one-to-one ratio. The resolution of the image is 0.03 in. (auth)
Date: April 1, 1962
Creator: Beck, W.N.
Partner: UNT Libraries Government Documents Department
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CHEMICAL PROCESSING OF COATED PARTICLE FUELS

Description: BS>Laboratory studies on the processing of graphite-base fuel elements containing pyrolytic carbon- or Al/sub 2/O/sub 3/-coated particles are reviewed. Potential processes for recovering U and Th from irradiated elements include grinding followed by acid leaching, and, burning and subsequent dissolution of the oxide ash. Disintegration in 90% HNO/sub 3/ was briefly evaluated as a method for determining the integrity of coated particles dispersed in graphite matrices. (auth)
Date: April 1, 1962
Creator: Ferris, L.M.
Partner: UNT Libraries Government Documents Department
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MODIFICATION OF THE EXPERIMENTAL BOILING WATER REACTOR (EBWR) FOR HIGHER- POWER OPERATION

Description: Supplement to ANL-5607. Alterations and additions made to the Experimental Boiling Water Reactor (EBWR) plant to permit operation at power levels up to I00 Mw(t) are described. Topics covered include over-all system modifications and additions, nuclear component modifications and additions, and reboiler plant component description. (M.C.G.)
Date: April 1, 1962
Creator: Matousek, J.F. comp.
Partner: UNT Libraries Government Documents Department
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SODIUM MASS TRANSFER: III. THE APPLICATION OF LIQUID AMMONIA AS A SODIUM LEACHING AGENT

Description: A technique is presented for liquid ammonla leaching of metallic sodium from corrosion coupons, filter elements, and sodium samples to reveal contaminants and impurities. The advantages of the method in preserving the physical form of corrosion or mass-transfer deposits are demonstrated. A possible application to the determination of trace oxygen in sodium is mentioned. (auth)
Date: April 1962
Creator: Alter, H.W. & McManus, P.A.
Partner: UNT Libraries Government Documents Department
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An Investigation of the Corrosion Resistance of Brazing Alloys for Austenitic Stainless Steel Fuel Elements for Service in 565 F Pressurized Water

Description: Since brazing was the method selected for joining the stainless steel SM- l reactor fuel element, corrosion studies were conducted on various potential brazing alloys to evaluate their resistance under the approximate pressurized- water conditions of the SM-1. The program consisted mainly of testing type 304L stainless steel T'' joints brazed with selected alloys in quiescent, degassed, and deionized autoclaved water at 565 deg F under 1200-psi pressure. In the initial phase of the investigatio… more
Date: April 12, 1962
Creator: Beaver, R. J.; Leitten, C. F. Jr. & English, J. L.
Partner: UNT Libraries Government Documents Department
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STABILIZING SRE FUEL ELEMENTS

Description: No Description Available.
Date: April 15, 1962
Creator: Donohue, H.F. & Vislay, H.A.
Partner: UNT Libraries Government Documents Department
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IRRADIATION OF A U-2% Zr FUEL TUBE IN THE VBWR

Description: A coextruded 2-inch-diameter tubular fuel element of U-2 wt% Zr alloy clad with Zircaloy-2 was irradiated in the Vallecitos Boiling Water Reactor to 1280 Mwd/t burnup with a maximum core temperature of 433 deg C. The purpose of this irradiation was to determine the dimensional stability of the alloy under conditions approaching those contemplated for D/sub 2/O-cooled power reactors. Successive dimensional measurements revealed a sharp change in swelling rate between 700 and 1280 Mwd/t burnup. T… more
Date: April 1, 1962
Creator: Quigley, H.C.
Partner: UNT Libraries Government Documents Department
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PL-3 Project Quarterly Progress Report, January 1, 1962-March 31, 1962

Description: Progress is reported on phase II in sections on final design, procurement, fabrication, testing, packaging, and crew training. A summary of completed phase I work on concept evaluation and preliminary design is also included. (J.R.D.)
Date: April 10, 1962
Creator: Humphries, G. E.
Partner: UNT Libraries Government Documents Department
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Specifications and Fabrication Procedures for Type 3 Fuel Elements

Description: Process and product requirements to be met in the fabrication of Type 3 fuel elements are presented. The fuel elements specified consist of thin plates of a dispersion of highly enriched UO/sub 2/ and ZrB/sub 2/ in a stainless steel matrix which is clad with stainless steel on all surfaces. Quality assurance provisions are discussed. Process and material specifications and packaging and packing for shipment are described. Sample calculations and drawings are included. (M.C.G.)
Date: April 27, 1962
Creator: Edgar, E. C. & Clayton, H. R.
Partner: UNT Libraries Government Documents Department
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DIRECTIONS FOR THE FABRICATION OF A PROBE FOR THE MEASUREMENT OF PLATE SPACING IN PLATE-TYPE FUEL ELEMENTS

Description: A probe for measurement of the space between fuel plates in high-burnup MTR-type fuel elements by eddycurrent techniques is described/su The sensing section is supported near the end of a flattened stainless steel tube into which a rectangular hole was cut to receive it/su The sensing section consists essentially of two slightly bowed springs, the midsections of which protrude slightly above the upper and lower surfaces of the flattened tube. Each spring- carries a section of a ball bearing as … more
Date: April 11, 1962
Creator: Dismuke, S.E.
Partner: UNT Libraries Government Documents Department
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