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Use Test Comparison of TBP Diluents

Description: Several diluents for possible use in TBP Purex Plant solvent were tested. The tests included nitric --nitrous acid degradation, fission prcduct distribution under simulated plant conditions, emulsillcation, and radiolysis. The order of quality of four diluents is n-dcdecane> Soltrol 170> Shell Code 85030(82000)> Shell E-2342. (D.L.C.)
Date: July 1, 1961
Creator: Mendel, J. E.
Partner: UNT Libraries Government Documents Department
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The Thermodynamic Properties of the Alkali Halides

Description: The thermodynamic properties of the alkali halides are reviewed, presenting data supplementary to that of Brewer and Brackett, Chem. Rev. 61: 425-432(1961). (T.R.H.)
Date: November 1961
Creator: Brewer, L.
Partner: UNT Libraries Government Documents Department
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LITHIUM HYDRIDE PROPERTIES

Description: A tabulation is presented of values for selected properties of lithium hydride. (M.C.G.)
Date: March 14, 1961
Creator: Welch, F.H.
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report (for) July 1961

Description: A summary is presented of activities in reactor and general engineering research programs. Discussions are included for developments in EBWR, BORAX-V, ZPR-III. ZPR-VI, ZPR-IX, EBR-I, and EBR-II. Reactor safety studies were performed for fast and thermal reactors. Nuclear technology developments are discussed for applied nuclear and reactor physics, reactor fuels and materials development, heat engineering studies, separations processes, and advanced reactor concepts. (B.O.G.)
Date: August 15, 1961
Partner: UNT Libraries Government Documents Department
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Material Buckling Measurements on Graphite-Uranium Systems at Hanford: A Summary Tabulation

Description: Measurements of material bucklings for graphite uranium systems are summarized. A comprehensive listing and guide to the original data sources is provided. Complete information on physical and nuclear properties of the lattice and the geometry of the exponential assembly is included, along with some of the auxiliary data taken. The fuel sizes vary from 0.925 to 2.5 in. in diameter for five different fuel geometries. The lattice spacings vary from 4 3/16 to 15 in. Over 300 measurements of materi… more
Date: May 1, 1961
Creator: Wood, D. E.
Partner: UNT Libraries Government Documents Department
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Remote Plastic Bag Passout Unit for High-Level Radiochemical Operations

Description: A system is designed for making remote sealed-bag passouts from a multicurie-level chemistry processing enclosure. The polyethylene bags are changed remotely without exposing contaminated surfaces while always maintaining a low leak rate seal. The system employs an interchange box (passout box) attached to the chemistry enclosure. Integrated with the box is a hydraulically operated jack that raises and lowers the bags, and a welder-cutter for sealing them. A single master-slave manipulator team… more
Date: August 1, 1961
Creator: Fleischer, E. S.; Parsons, T. C. & Howe, P. W.
Partner: UNT Libraries Government Documents Department
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EXTRACTION OF NEPTUNIUM FROM ACIDIC SOLUTIONS BY ORGANIC NITROGEN AND PHOSPHORUS COMPOUNDS

Description: Neptunium distribution coefficients from acid nitrate, chloride, and sulfate solutions by several organic nitiogen and phosphorus compounds were measured as functions of several extraction variables, including neptunium valence, acid and salt concentration, and reagent concentration. Extractability by all the reagents varied in the order Np(IV)> Np(VI)>> Np(V). Except for primary amines, all reagents extracted Np(IV) much more strongly from nitrate than sulfate solutions. Among organonitrogen c… more
Date: October 19, 1961
Creator: Weaver, B.
Partner: UNT Libraries Government Documents Department
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Hazards Report for the BF3 Withdrawal Mechanism in the SM-1

Description: A design and operational description is presented of a BF/sub 3/ withdrawal mechanism planned for installation on one of the two startup channels at the SM-1. An analysis of possible malfunctions is included. (J.R.D.)
Date: October 13, 1961
Creator: Coombe, J. R.
Partner: UNT Libraries Government Documents Department
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RADIOISOTOPE AND RADIATION APPLICATIONS QUARTERLY PROGRESS REPORT. SECTION I. USE OF INTRINSIC RADIOACTIVE TRACERS FOR PROCESS CONTROL. SECTION II. RADIATION-INDUCED GRAFT-POLYMERIZATION STUDIES

Description: Research was continued in the areas of intrinsic radioactive tracers for industrial process control and the influence of structural factors in radiation- induced graft polymerization. The use of in-process isotope neutron soarces to produce short-lived radiotraces is discussed. A 10c Po--Be neutron source was obtained for exploratory experiments. The design and construction of a neutronsource storage shield and an activatioa-cell holder are underway. The effect of structural factors oii the eIf… more
Date: October 23, 1961
Creator: McFarling, J.L.; Gluck, P.; Kircher, J.F.; Sunderman, D.N.; Sliemers, F.A.; Luttinger, M. et al.
Partner: UNT Libraries Government Documents Department
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Dimensional Behavior of the Experimental Gas-Cooled Reactor Fuel Element at Elevated Temperatures

Description: The Experimental Gas-Cooled Reactor (EGCR) fuel assemblies consist of a cluster of seven fuel elements contained in a graphite sleeve. Each element is composed of hollow cylindrical UO/sub 2/ pellets encapsulated in a type 304 stainless steel tube. The dimensional behavior of the fuel element was determined in an apparatus which simulated the thermal conditions predicted for the EGCR. Particular emphasis was placed on determining the relationship between the fuel temperature and axial expansion… more
Date: August 1, 1961
Creator: Martin, W. R. & Weir, J. R.
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF PLUTONIUM BEARING FUEL MATERIALS. Progress Report for Period April 1 through June 30, 1961

Description: BS>Activities are discussed for work done in the preparation of PuO/sub 2/ using the continuous oxalate process, and continuous coprecipitation studies using a uranium-20 wt% plutonium nitrate feed solution. Characterization studies of the PuO/sub 2/ powders indicated that variations in the processing variables can affect the final product. Measurements with the B. E. T. and Innes apparatus confirmed that the specific surface area of the initial batch of the PuO/sub 2/ powder had increased appr… more
Date: October 31, 1961
Partner: UNT Libraries Government Documents Department
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THE EFFECTS OF INTERNAL HEAT GENERATION ON POT CALCINATION RATES FOR RADIOACTIVE WASTES

Description: Methods by which the radial deposition mechanism was determined in experiments with simulated waste solutions are reviewed. Based on this mechanism, an expression for the rate of solid deposition with internal heat generation was developed by a combined heat and material balance. A sample calculation for Purex waste showed that a moderate heat generation rate of 5000 Btu/hr/ft/sup 3/ would decrease the time to fill a 12-in.-dia calcination vessel from 78 to 55 hr. For the calcination stage of t… more
Date: October 23, 1961
Creator: Perona, J.J.
Partner: UNT Libraries Government Documents Department
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Upper Atmosphere Re-Entry Study High Altitude Burnup. Volume 2

Description: Methods of determining the fate of radioactive fuels in space power units burned up on re-entry into the earth's atmosphere are reviewed. Particulate characteristics experiments were derived from an analytical study on the ablation of Dlutonium fuel. This study revealed that the particulate size distribution resulting on re-entry burnup is a function of: the fuel form in use and the material velocity and atmospheric density at the time the fuel is exposed. The particulate fate experiments were … more
Date: January 1, 1961
Partner: UNT Libraries Government Documents Department
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THE PHYSICS DESIGN OF THE EBR-II

Description: The physics design problems of the EBR-II are summarized. These include analysis of the EBR-II engineering design as well as applicable zero-power critical experiments. Pertinent reactor safety problems are reviewed. Safety considerations bearing on normal plant operation and manipulations within the reactor are emphasized. The implication of controlled in-pile meltdown experiments is considered. Irradiation damage and metallurgical phase phenomena are summarized and related to reactivity. The … more
Date: July 1, 1961
Creator: Loewenstein, W.B.
Partner: UNT Libraries Government Documents Department
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Steady State and Transient Thermal and Hydraulic Analysis of SM-2 Termination Report

Description: Thermal characteristics of the SM-2 core were analyzed at steady state and loss of flow conditions. For steady state operation, the steady state code STDY-3 was used. For transients during-a loss of flow acident, ART-02, a onedimensional code, was used. This analysis indicated the SM-2 core is safe from burnout under steady state operation at design power level (28 Mw(t)) because no nucleate boiling exists, and the minimum burnout ratio is above 2.0. The core is safe from burnout under loss of … more
Date: September 1, 1961
Creator: Segalman, I. & Bradley, P. L.
Partner: UNT Libraries Government Documents Department
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Evaluation of Hydrocarbon Diluents for the Purex Process

Description: Forty-nine hydrocarbon products were evaluated in the laboratory in a search for a highly stable diluent for the organic extractant used in a radiochemical separations plant. The formation of zirconium ligands during chemical and radiolytic degradation increased with boiling point for isoparaffinic producte but was approximately constant for n-parafiins. Of those materials that met the local flash point specification, the n-parafiins were superior. (auth)
Date: November 1, 1961
Creator: Dennis, B. P. & West, D. L.
Partner: UNT Libraries Government Documents Department
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Periodic Waste Disposal System Material Balance Test. Core 1, Seed 2. Test Evaluation T-641317. Section 1

Description: A test was carried out to determine the adequacy of storage capacity and operating procedures of the radioactive waste disposal system during a normal reactor plant warmup. The capacity and operating procedures were found to be adequate. It was impossible to perform a complete material balance based on existing level instrumentation and using the data required by the test procedure. Approximately 21,290 gal. of waste were received in the system and 13,210 gal. were discharged to the river with … more
Date: June 30, 1961
Partner: UNT Libraries Government Documents Department
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