102 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "Metals, Ceramics, And Materials"  
prev Results: 25 - 48 next
open access

A Study of the Effects of Fabricating Conditions on Some Properties of Sintered Uranium Monocarbide

Description: The effect of initial particle size (6.2 and 14.7 mu ), forming pressure (50,000 and 100,000 psi), temperature (1600 and 1800 deg C), and time at temperature (1 and 3 hr) on the bulk density, grain size, and porosity of sintered uranium monocarbide compacts was studied, Within the limits of the variables studied there appeared to be no significant changes in these properties of the sintered material attributable to the changes in the fabricating conditions. (auth)
Date: October 1, 1959
Creator: Tripler, A. B., Jr.; Snyder, M. J. & Duckworth, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Casting Development for Uranium-Molybdenum Alloy Shapes

Description: The casting of shapes of uranium--molybdenum metal of varying sizes and thicknesses from a molten charge has been successfally accomplished with specificially designed graphite distributors and molds. Solid cylinders, hollow cylinders, and flat plate shapes were cast in gang molds. As many as 35 solid cylinders have been cast simultaneously. All castings had smooth surfaces, and solid shapes were cast to 0.006-in. tolerance on all dimensions except length. (auth)
Date: November 15, 1959
Creator: Binstock, M. H. & Stanley, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

ZIRCONIUM CLADDING OF URANIUM

Description: Under proper conditions of vacuum and mold preheat, a sound ductile alloy bond can be achieved by casting molten uranium into zirconium and Zircaloy- 2 molds. Investigations indicate that a process for production of zirconium of Zircaloy-2 clad fuel elements can be developed by casting directly into preformed shells. Employment of cast bonding techniques appears to be a simple and practical method for assembling extrusion billets. It also appears that coextrusion of cast bonded normal uranium b… more
Date: November 1, 1954
Creator: Pankaskie, P. J. & Schaffer, L. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Uranium Dioxide-Stainless Steel Specimens for Irradiation in Sodium- Experiment PW-5-1

Description: The preparation, pre-irradiation testing, and encapsulation of stainless- U cored, plate-type fuel elements for irradiation in;tagnant sodium are discussed The eight specimens for Experiment PW-5-1 are examined. (auth)
Date: April 25, 1955
Creator: Calkins, G. D.; Pobereskin, M.; Keeler, J. R. & Keller, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

AN ESTIMATION OF THE EXPLOSION HAZARD DURING REPROCESSING OF METALLIC URANIUM FUEL ELEMENTS METALLURGICALLY BONDED TO ZIRCALOY CLADDING

Description: BS>Experimental studies were performed to define the behavior in ammonium fluoride solutions of uraniumzirconium alloys and of explosive residues isolated from such alloys. The results indicate that once the diffusion layer existing between the uranium core and the Zircaloy cladrung is exposed to such solutions, it will readily and completely dissolve, thus eliminating the possibility of this portion of the diffusion layer entering into an explosive reaction with nitric acid. Because of the pro… more
Date: September 30, 1959
Creator: Swanson, J.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effects of High Burnup at Elevated Temperatures on Uranium-0.52 and 1.62 w/ o Zirconium Alloys. Final Report of Metallurgy Program 6.1.16

Description: An investigation of the effects of irradiation on uranium containing 0.52 and 1.62 wt.% zirconium was made. Specimens of wrought material, variously heat treated, were studied as well as castings of the alloys. It was found that, although the wrought and heat-treated alloys were reportedly stable under thermal cycling, they elongated rapidly under irradiation. The best material studied was the 1.62% alloy in the as-cast condition. It was found to increase in length initially at a rate of about … more
Date: August 1, 1959
Creator: Kittel, J. H. & Paine, S. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Diffusion of Hydrogen in Zirconium Hydride

Description: The diffusion of hydrogen in zirconium hydride was studied using permeation techniques. The rate of permeation of hydrogen through zirconium hydride disks was measured for small concentration gradients. Data were obtained at 61 to 65 at.% hydrogen and 500 to 750 ction prod- C. The diffusion coefficients were determined by the time-lag method. Ho variation of the diffusion coefficients with hydrogen concentration was observed. The diffusion coefficients can be expressed by D (cm/sup 2/ per sec) … more
Date: March 1, 1960
Creator: Albrecht, W. M. & Goode, W. D., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effect of Additions to Zircaloy on Hydrogen Pickup During Aqueous Corrosion

Description: An investigation was conducted into the possibility of alloy additions to Zircaloy-2 to diminish hydrogen absorption during aqueous corrosion. The nickel in Zircaloy-2 is believed to be the major constituent responsible for the relatively high hydrogen absorption. Additions of up to 0.5 wt.% antimony, arsenic, bismuth, or tellurium were selected on the basis of their known ability to poison the catalytic effects of nickel in hydrogenation reactions of other systems. Results of tests conducted f… more
Date: December 29, 1959
Creator: Berry, W. E.; White, E. L. & Fink, F. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Thermal Expansion of Synthetic Graphites at Temperature Intervals Between 80 and 2000f

Description: The mean linear and cubical coefficients of thermal expansion of eight commercial samples of graphite were determined for temperature intervals between 80 and 2000 deg F. The linear thermal expansion was measured with an automatic recording dilatometer using a rod-shaped specimen 2 in. long and 1/4 in. across. The specimen was heated in an atmosphere of helium. The results were in good agreement with those of Currie, Hamister, and MacPherson. The mean linear coefficient was found to increase wi… more
Date: November 30, 1959
Creator: Allen, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Examination of Jacketed Uranium Slugs from the Los Alamos Fast Reactor "Clementine"

Description: Examination of clad uranium reflector slugs wbich falled by rupture and swelling during the first year of operation of Clementine revealed no anisotropic damage to the uranium because of burnup or thermal cycling. The cladding was found to be of high-sulfur-free-machining steel, and it is postulated that thermal stresses caused welding flaws to open enough to permit seepage and corrosive attack upon the uranium cores by the reactor coolant (mercury). (auth)
Date: October 1, 1959
Creator: Paine, S. H.; Murphy, W. F. & Brown, F. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

VANADIUM-CHROMIUM ALLOY SYSTEM

Description: On the basis of data obtained from melting point determinations, microscopic examination, and x-ray investigations, a phase diagram is proposed for the V-Cr alloy system The system forms a complete series of solid solutions with a minimum occurring in the solidus at 1750 deg C and approximately 70 wt.% Cr. No intermediate phases were found in this system. Hardness and corrosion data are presented as a function of alloying composition. (auth)
Date: November 1, 1959
Creator: Carlson, O.N. & Eustice, A.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

ELECTRODEPOSITION OF NICKEL ON URANIUM

Description: Electrodeposited nickel coatings on uranium for protection from destructive corrosion in boiling water wns investigated. Correlation between the pretreatment of the uranium and subsequent protection by thin nickel coatings was established. Thin electrodeposited nickel coatings provide better protection when applied to a matte surface produced by blasting with an aqueous suspension of silica (100 mesh) followed by a cathodic treatment in 35 wt% sulfuric acid than when applied to the rough surfac… more
Date: August 31, 1954
Creator: Beard, A. P. & Crooks, D. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Corrosion of Stainless Steel in Thorex Process Solutions

Description: The corrosion of 304L and 309SCb stainless steel was studied in HF--HNO/ sub 3/ solutions proposed for the Thorex process. Except for the dissolving and waste evaporation steps in the Thorex process, corrosion of 304L and 309SCb is not expected to exceed that experienced in the Purex process. To minimize the high initial corrosion rate of 309SCb in the boiling HF-- HNO/sub 3/ dissolving solution, a heel of thorium should be maintained in the dissolver. The corrosion rate of 304L in the low acti… more
Date: December 1, 1959
Creator: Kranzlein, P. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Mechanical Properties of Uranium Plate

Description: Hot-rolled uranium plate exhibited a pronounced directionality in mechanical properties which was reduced but not eliminated by beta transformation. Results of tensile, bend, impact and hardness tests made at room temperature are summarized for both hotrolled and beta-transfomned uranium plate. Significant differences in mechanical properties existed between ten lots of uranium plate processed under similar conditions. Composition and processing data were inadequate to assign causes for the var… more
Date: June 1, 1959
Creator: Caskey, G. R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

MODIFICATION OF CP-5 FUEL ASSEMBLIES FOR FUEL CAPSULE IRRADIATION EXPERIMENTS

Description: BS>The standard vertical fuel tube assembly of the CP-5 research reactor was modified to permit diversion of heavywater coolant into the thimble for temperature-controlled irradiation experiments of capsules containing fuel specimens. The modification entailed revisions to the thimble, outer top shield plug and center shield plug. and helium sweep system. The modified thimble is provided with inlet actor flow system through the thimble cavity. The coolant in the thimble removes fission heat fro… more
Date: November 1, 1959
Creator: Beck, W.N.; Kittel, J.H. & Brown, F.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Method of Correlating Irradiation Effects in Dispersion Fuels

Description: A method of correlating irradiation effects in dispersion fuels was proposed in which the effects of irradiation conditions are considered independently of material variables. Two simple failure models were devised (failure by creep and by short-term stress yield). Criteria which permit estimates of the relative severity of tests made under different test conditions but on identical specimens were developed. Numerical application of the procedures for 18-8 stainless steel with 25 and 30 wt.% UO… more
Date: January 20, 1960
Creator: Keller, D. L.; Hulbert, L. E. & Dunnington, B. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

DEVELOPMENT AND PRODUCTION OF URANIUM 10 wt.% MOLYBDENUM AS-CAST SLUGS FOR HNPF PHYSICS EXPERIMENT

Description: A multiple casting process was developed for the production of 0.590 plus or minus 0.005-in. diam. by 12-in. long solid right cylinders. The process involves vacuum induction melting in MgZrO/sub 3/ coated graphite crucibles and casting into coated graphite molds. Thirty-eight hundred fifty 90 wt.% U of 1.5 wt.% enrichment-10 wt.% Mo as-cast pins were produced for HNPF Exponential Experiments. (auth)
Date: April 1, 1960
Creator: Stanley, J.A. & Binstock, M.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Corrosion of Plutonium Alloys in Nak

Description: A Pu-Al alloy containing 4 at. % Ad showed no attack after exposure to purified NaK for one month at 400 deg C in the absence of any oxide. The same specimen and other Pu alloys, including pure Pu, showed marked deterioration in shorter exposures in the presence of oxide fllms from a welded stainless steel container. Pure U was found to be resistant in the presence of such oxides. (auth)
Date: July 1, 1953
Creator: Hyman, H. H. & Katz, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HIGH-TEMPERATURE IRRADIATION ON A ZIRCONIUM HYDRIDE-2 w/o URANIUM ALLOY

Description: Enriched ZrH/sub 1.65/ -2 wt.% uranium specimens were irradiated under 1 atm. of hydrogen at center-line temperatures between 900 to 1400 deg F to uranium burnups of between 13 and 25 at.%. Specially designed irradiation capsules were used to provide the conditions of temperature and hydrogen atmosphere which were required. Each capsule was instrumented with five thermocouples so that ample temperature data could be obtained during the irradiation. Almost negligible density changes were produce… more
Date: December 10, 1959
Creator: Lamale, Gerald E.; Hare, Alan W.; Krause, Horatio H.; Hopkins, Alan K.; Stang, John H.; Simons, Eugene M. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effects of High Neutron and Gamma Fluxes on the Transmission Characteristics of Some Optical Glasses

Description: The design of the Sandia Engineering Reactor Facility (SERF) presented a unique problem of finding a way to view the virtually unshielded 5 Mw reactor during operation. It was determined that periscope viewing was most feasible. The front optical elements of the periscope must withstand a total integrated radiation dose of 3 x 10/sup 9/ of gammas, and 1.4 x 10/sup 7/ n/cm/sup 2/, without excessive transmission losses. A program started to study the effects of radiation at such rates and total d… more
Date: November 1, 1959
Creator: Colp, J. L. & Woodall, H. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THE SOLID SOLUBILITY AND CONSTITUTION OF YTTRIUM IN IRON-20 TO 40 w/o CHROMIUM ALLOYS

Description: The solid solubility of yttrium in iron-20 to 40 wt.% chromium alloys was determined by metallographic techniques and found to be extremely small. At 1320 deg C, the maximum solubility is about 0.12 wt. a yttrium. Study of iron- rich alloys of the iron-yttrium system shows that the compound YFe/sub 5/ exists. A eutectic occurs between iron and YFe/sub 5/ at 1257 deg C. The constitution of iron - 20 to 40 wt.% chromium-yttrium alloys ccntaining less than 6 wt.% yttrium was studied between 1250 a… more
Date: October 20, 1959
Creator: Farkas, Martin S. & Bauer, Arthur A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Zirconium Highlights

Description: The testing of Zircaloy at various stages of processing by ultrasonic techniques is described A study was made to determine the feasibility of substituting ammonium bifluorlde for the liquid hydrofluoric acid generally used in the etching processes required for the fabrication of Zircaloy fuel coniponents The addition of B to Zr results in a very strong alloy however. they show little proniise for being ductile. Zirconium-boron alloys can be hot forged Boron is very detrimental to the oxidation… more
Date: January 1, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HYDROGEN PICKUP DURING CORROSION OF ZIRCONIUM ALLOYS

Description: Several factors such as alloy composition, hydrogen content of the alloy, surface hydrides, and hydrogen content of the water have been investigated for their effect upon the amount of hydrogen picked up by zirconium alloys during corrosion in 680 deg F water. Metallic additions of nickel increase hydrogen pickup, antimony, chromium, and iron appear to decrease the hydrogen pickup, while the addition of tin has little or no effect. The hydrogen content of the metal (50 to 400 ppm) or of the wat… more
Date: September 24, 1959
Creator: Berry, W.E.; Vaughan, D.A. & White, E.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen