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Temperature-Induced Stresses in Solids of Elementary Shape

Description: Report discussing how solids subjected to non-uniform temperature change develop internal stresses determined by, (1) the temperature distribution within the solid, and (2) certain physical constants of the material. For two varieties of heating, the equations determining stress have been put in convenient form for practical use, and tables of certain temperature functions show how to determine stresses in a slab, in a cylinder, or in a sphere subjected to either of two modes of heating. The temperature-distribution tables independently provide a useful means for the ready estimation of temperature gradients.
Date: June 21, 1960
Creator: Adams, Leason H. & Waxler, Roy M.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Supplement to "Studies on the Equilibrium Temperature for the Plutonium Alpha-Beta Transformation"

Description: The cited paper presents data which establishes the equilibrium temperature for the alpha-beta transformation of Pu at 117.0 ±0.5°C. This was observed by following the electrical resistance change in thin, high purity, mixed-phase specimens as they were thermally cycled near the transformation temperature. As expected the time required for small phase changes near the equilibrium temperature was long. Data regarding the mechanisms of the alpha-beta and beta-alpha transformations or rates as a function of temperature were not presented.
Date: December 21, 1965
Creator: Anderson, J W
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mixing of a Cold Liquid Jet With a Boiling Liquid Stream

Description: The turbulent mixing of a cold liquid jet with a stream of vapor bubbles and saturated liquid is analyzed for a single axial liquid jet. The cases where the issuing jet velocity is very much greater than and nearly equal to the free stream velocity are considered. Transport of axial momentum and of scalar quantities in the stream are calculated and the results applied to the transport of enthalpy in a bubbly mixture. (D.L.C.)
Date: October 21, 1960
Creator: Bankoff, S. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production test authorization: 011 HDS and ALSI fuel performance monitoring

Description: Much useful information has been gained from this program, leading to improvements and additions to non-destructive testing equipment, improved fuel quality, and a generally better understanding of fuel performance. The original objectives of the program have been met -- at least to the extent that such information can now be effectively used. However, other aspects of the program have a continuing value. Visual examination and dimensional data obtained routinely on production fuels have been a useful tool as a monitor of reactor conditions and trends, and of fuel quality. This test authorization proposes to continue a PT-216 type of program, modified to better serve today`s needs.
Date: March 21, 1966
Creator: Bears, R.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TABLE OF ELECTRONIC RADIAL FUNCTIONS AT THE NUCLEAR SURFACE AND TANGENTS OF PHASE SHIFTS

Description: Tables of electronic radial functions are presented. The finite nuclear size effects and the finite deBroglie wave length effects were incorporated in this work. A brief summary of the formulation of the problem is given. (M.C.G.)
Date: December 21, 1961
Creator: Bhalla, C.P. & Rose, M.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Survey of Recent Developments in Solvent Extraction With Tributyl Phosphate

Description: Tributyl phosphate can be used for extraction in processing all current power reactor fuels. Nitric acid is the only salting agent required. Typical flowsheets are presented. In aluminum nitrate systems which are more than 0.1 M acid deficient, the uranium distribution coefficient is a function of pH and independent of aluminum concentration; the coefficient remains constant at one in fluoride systems when the nitrate to fluoride ratio is approximates 3.5. Many objectionable properties of degraded diluents are ascribed to nitroparaffins. Aliphatic diluents with the least branching are the most stable to nitration. The nitration stability of aromatic diluents varies with structure, e.g., stabilities of diethylbenzenes decrease as meta >> ortho > para. Solvent purification by flash distillation appears superior to other methods. The stability of Amsco 125-82 was permanently improved by treatment with sulfuric acid. The radiation stability of TBP was approximates 2 times higher in an aromatic diluent than in Amsco 125-82. The G decomposition value for 1 M TBP in Amsco alone was approximates 0.9; whereas in 1 to 3 M HNO/sub 3/ it was 1 to 5 and G (--HNO/sub 3/ org phase) was 3 to 20. Variation of uranium--thorium separation factors with structure of some neutral organophosphorus reagents is presented. Basic studies include measurement of activities in multicomponent solutions and description of aqueous activity coefficients by an extended Debye- Huckel equation. (auth)
Date: March 21, 1963
Creator: Blanco, R. E.; Blake, C. A., Jr.; Davis, W. Jr. & Rainey, R.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EVALUATION OF ULTIMATE DISPOSAL METHODS FOR LIQUID AND SOLID RADIOACTIVE WASTES. PART III. INTERIM STORAGE OF SOLIDIFIED WASTES

Description: The costs of interim storage of solidified Purex and Thorex wastes in water-filled canals were estimated as the third part of a study to evaluate, from the standpoint of econoNonemics and hazards, the various steps leading to and including the permanent disposal of highly radioactive liquid and solid wastes. The wastes were assumed to have been solidified following their production in a plant proccessed 1500 metric tons per year of uranium converter fuel it a burnup of 10,000 Mwd/ton and 270 tons/yr of thorium converter fuel at 20,000 Mwd/ton. Separate facilities where designed for the storage of the calcined wastes in the acid and reacified forms, and for the Thorex waste made into a glass. Consideration was given also to storage (in the same facilities) of the combinations acid Purex-acid Thorex and reacified Purex-reacidified Thorex wastes. Costs for interim storage times from 1 to 30 yr were computed for wastes decayed 120 days and 1, 3, and 10 yr at time of initial storage. Costs ranged from 1.5 x 10/sup -3/ mill/kwh, for 1-yr storage of calcined 10-yr-old acid Purex waste to 18 x 10/sup -3/ mill/kwh/sub e/ for 30-yr storage of calcined, reacified 120-day- old Thorex wastes. Costs of storage of the Purex and Thorex wastes together in the same facility ranged from 1.5 x 10/sup -3/ mill/kwh/sub e/ for 1-yr storage to 4.8 x 10/sup -3/ mill/kwh/sub e/ for 10-yr storage for the calcined acid wastes and from 1.8 x 10/sup -3/ to 6.3 x 10/sup -3/ wastes at time of storage was not a very significant factor, the costs for storage of 10-yr-decayed wastes being only 10 to 15% less than those for storage of the same wastes aged 120 days. Storage of acid wastes as solids was cheaper by factors of 2 to 2.7 than storage …
Date: October 21, 1963
Creator: Blomeke, J O; Perona, J J; Weeren, H O & Bradshaw, T L
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Ingot-dingot comparison

Description: For approximately the past two years, alloyed dingot uranium has been irradiated on a production scale for evaluation of rupture performance relative to ingot uranium. Supplementary data on dimensional behavior and certain pre-irradiation measurements have been accumulated under the Quality Certification Program. This report presents a comparison of ingot and dingot performance based on data obtained to date from this testing program. The discussion consists of three sections: (I) dimensional stability, (II) external bond quality, and (III) reactor rupture performance.
Date: May 21, 1962
Creator: Bloomstrand, R. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Proposal: Direct ingoting of unpickled buttons for economic and product quality gains

Description: The final product from the Reduction Operation at the present time is an unalloyed button of reasonably high purity and density. Considerable effort is being directed toward improvement of button purity and surface finish, or appearance. A direct ingoting step is proposed in place of button pickling as a practical means of improving metal quality and appearance. A second ingoting step is proposed to further improve process economics through improved radiographic integrity. Ingoting of buttons immediately following reduction appears to be a more direct and practical approach to definition and improvement of metal purity and improvement of product appearance. The proposed process change places button ingoting within the scope of the Reduction Operation. The final product from the Reduction Operation will then be an ingot of uniform composition (no segregation), reliable density and plutonium content (no slag inclusions or voids). The ingot could be subdivided in this operation, ready for Foundry use; or it could be cast as an ingot of assured quality for off-site shipment.
Date: September 21, 1964
Creator: Bond, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Proposed process test to evaluate direct ingoting of unpickled buttons

Description: A proposal has been made for ingoting of buttons, without pickling, immediately after breakout from the reduction vessel. This proposed process change could enable the substitution of an ingot of definable, high purity, and good appearance in place of a button as the final product of the Reduction Operation. The change should also achieve economic advantages and decrease radiation exposure. The packaging and storage of the resultant high-grade ingot will require a change of storage container from that presently used to eliminate plastic materials. High-grade plutonium metal corrodes rapidly when packaged in plastic. The ingots, to be prepared in the process test described below, provide an opportunity for testing of a revised, organic-free storage container. The purposes of this process test do not depend on the nature of the buttons processed, hence the tests could be run with unalloyed buttons or with alloyed buttons (RAB), as current FAB needs dictate.
Date: September 21, 1964
Creator: Bond, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Conductive Flooring for Hospital Operating Rooms

Description: Report issued by the Bureau of Standards over studies on the importance of conductive flooring in hospitals. Types of conductive flooring are compared, and tested. The methods and results are presented, and discussed. This report includes tables, illustrations, and photographs.
Date: March 21, 1960
Creator: Boone, Thomas H.; Hermach, Francis L.; MacArthur, Edgar H. & McAuliff, Rita C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Digital Comparator

Description: A digital comparator has been designed to flag data which goes above a maximum limit or below a minimum limit.
Date: September 21, 1960
Creator: Bourgeois, N. A., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HYDROLYSIS OF URANIUM CARBIDES BETWEEN 25 AND 100 . II. AS-CAST ALLOYS CONTAINING 2 TO 10 WT % CARBON

Description: Reactions with water of as-cast uranium-carbon alloys containing 2to 10 wt% carbon (UC/sub 0.4/ to UC/sub 2.2/) were investigated by using gas- chromatography for analysis of the gaseous products. Uranium metal-uranium monocarbide alloys yielded 2 moles of free hydrogen per mole of free metal, in addition to methane, small quantities of higher molecular weight gaseous hydrocarbons, and a solid, hydrous, tetravalent uranium oxide. The gaseous producte contained all the carbon originally present in the alloy. Uranium dicarbide (UC/sub 1.86/; this combined-C/U atom ratio was the maximum which could be obtained) yielded a mixture of 38 hydrocarbons (methane, 15 vol%; ethane, 28%: C/sub 3/- to C/sub 8/-alkanes, 7%; alkenes, 8%; alkynes, 0.6%; and widentified unsaturates, 1%), free hydrogen (40 vol%), a water-insoluble wax, and a solid, hydrous, tetravalent uranium oxide. Forty% of the combined carbon was found in the gas and 25% in the wax. The gaseous products from the hydrolysis of both UC and UC/sub 1.86/ were not affected by changes in the reaction temperature between 25 and 99 deg . The composition of the gases evolved at 80 deg from as-cast alioys with compositions between UC and UC/sub 1.86/ varied linearly with the combined-C/U atom ratio of the alloy; however, the amounts of methane produced were lower than expected from the UC concentrations in the alloys. (auth)
Date: January 21, 1963
Creator: Bradley, M.J. & Ferris, L.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Chemical Development Section C Progress Report for October-December 1961

Description: Recovery of Th (and U) from Granitic Rock. Recovery of Th by acid leaching ten addltlonal granite samples (36 to 82 ppm Th) from the Conway formation in N. H. ranged from about 50 to 85%, and averaged about 70%, Study of the effect of grind size on the recovery of Th from Conway and Plkes Peak granites showed no significant differences in the range minus 20 to minus 200 mesh. The Th concentration in a sized Conway granite sample was found to be much greater in the fine than in the coarse fractions, whereas Pikes Peak granite showed only slight Th enrichment in the finer fractions. U recoveries in acid leaching of four different granite samples were not improved by adding an oxidant. Collection and Analysis of Granite Samples. A field survey of the Conway granite formations in N. H. was made. Preliminary analysis of the data indicates that the accessible surface of the Conway granite averages at least 40 ppm Th. Collection and Analysis of Lateritic Soils. The Th concentration ranged 5 to 16 ppm in twenty-two samples of sub-lateritic soil from Miss., Ala., Ga., and Va. Final Cycle Pu Recovery by Amine Extraction. In continued batch countercurrent testing with simulated Purex 1BP solution of the proposed chemical flowsheet for final cycle Pu recovery by amine extraction, the extraction profile with the amine (TLA) concentration decreased from 0.3 to 0.15 M again confirmed the predicted extraction isotherm. The product solution contained 23 g Pu/liter (nominal x20 concentration factor), and the stripped organic and the raffinate contained, resp., 0.001 and <0.002 g/liter. Extraction and Separation of Zr and Hf. Results are summarized for tests on the extraction and separation of Zr and Hf with amines and organophosphorus esters and acids. All three extractant classes showed some promise but the …
Date: February 21, 1962
Creator: Brown, K.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Equation of State of Classical Systems of Charged Particles

Description: Recent developments in the classical theory of fully ionized gases and strong electrolyte solutions are reviewed, and are used to discuss the equation of state at high temperatures and low densities. The pressure is calculated using the ring-integral approximation, and quantitative estimates of higher correction terms are given. The effect of short range repulsive forces is shown by comparing the results with two kinds of potential functions hard spheres of diameter a, and soft'' spheres for which the short range potential cancels the Coulomb potential at the origin, and decreases exponentially with distance. It is found that the use of either type of potential extends the range of validity of the ring-integral approximation to considerably higher densities and lower temperatures. Since there is little difference in the results for the hard spheres and the soft spheres in this range, the latter system is investigated more extensively since it is more, easily handled by analytical methods. The expressions derived for the free energy of a system of charged particles can also be used in ionization equilibrium calculations, and the effect of electrostatic interactions on the equilibrium concentrations of various kinds of ions is indicated. 60 references. (auth)
Date: August 21, 1962
Creator: Brush, S.G.; DeWitt, H.E. & Trulio, J.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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