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in publisher: "General Electric Co. Hanford Atomic Products Operation, Richland, Wash."  
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A Study of the Kinetic and Mechanical Properties of a Stabilized Beta Phase Plutonium Alloy

Description: The elements Sn, Mg, Ti, Zr, Hf, Si, Cd, and U were alloyed with plutonium to determine their effect on stabilization of the beta phase. Zirconium was found to be the ' most effective. Kinetic studies were conducted on Pu-Zr alloys having 0.24, 0.65, and 1.7 at.% Zr contents. The beta to alpha transformation in the Pu-Zr alloys was somewhat similar to that in unalloyed plutonium. The main difference being that time, temperature, transformation curves of the alloys were shifted to the right as t… more
Date: January 1, 1962
Creator: Taylor, J. M.
Item Type: Refine your search to only Thesis or Dissertation
Partner: UNT Libraries Government Documents Department
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STUDIES IN MICROMERITICS. II. THE DEPOSITION OF PARTICLES IN CIRCULAR CONDUITS DUE TO THERMAL GRADIENTS

Description: The deposition of particles from turbulent gas streams due to thermal gradients was predicted using a simplified flow medel. In the medels particle concentration was assumed constant in the turbulent region. The particle deposition velocity was taken to be the radial velocity of thermal - repulsion in the laminar sublayer. Temperature gradients in the laminar sublayer were calculated for constant wall temperature using the Reynoldss analogy. The loss magnilude of suspended particles from loss d… more
Date: October 1, 1961
Creator: Postma, A.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HANFORD STUDIES FOR EGCR COMBUSTION CHARACTERISTICS. Summary Report

Description: The temperature, geometry, and flow conditions which exist in the EGCR were duplicated in a mock-up designated as the EGCR Burning Rig to establish the combustion conditions in the reactor. The conditions under which the EGCR Burning Rig will ignite were established and an analytical model was developed which predicts these conditions. Because the Burning Rig cannot exactly dupIicate the reactor situation the final prediction of the safety of the EGCR must rest on computer calculations employin… more
Date: October 10, 1961
Creator: de Halas, D.R.; Dahl, R.E. & Jackson, J.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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OXIDATION OF GRAPHITE UNDER HIGH TEMPERATURE REACTOR CONDITIONS

Description: A kinetic study was conducted to provide information on oxidation of reactor graphites in the temperature range of 450 to 675 deg C and on the effects of reactor environment on oxidation rates. Among the parameters studied were chemical reactivity of the graphite, prior oxidation, a high intensity gamma flux during oxidation, variation of the surface-to-volume ratio of the graphite specimens, neutron bombardment prior to oxidation exposure, and gas flow rates. Rate equations showed apparent act… more
Date: July 1, 1961
Creator: Dahl, R.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SIZE ANALYSIS OF PARTICULATES FOUND IN AIR AT HANFORD PLUTONIUM FABRICATION FACILITIES

Description: A study was made on the characteristics of radioactively contaminated air at Hanford work locations. One of the main objectives in this study is to define the size of particular air contamination in plutonium handling facilities. In addition to characterizing the particulate contamination, it is desirable to know the normal background particle size distribution. Data are summarized on general particle size distribution and radioactive particle distribution at two Hanford plutonium fabrication f… more
Date: August 1, 1962
Creator: Selby, J.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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LOADING AND ELUTION CHARACTERISTICS OF SOME NATURAL AND SYNTHETIC ZEOLITES

Description: The cation exchange characteristics of several commercially available zeolites were evaluated, Equilibrium loading characteristics and exchange capacities were determined experimentally in the binary systems cesium-lithium, cesium-- sodium, cesium--potassium, cesium-Tubidium, cesium -- hydrogen, cesium-- ammonium, strontium-- magnesium, strontium-- calcium, strontium-- barium, and strontium-- hydrogen for several zeolites. Exchangeable cation fractions in the equilibrium solutions were varied f… more
Date: August 10, 1962
Creator: Ames, L.L. Jr. & Knoll, K.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Salt Cycle Process

Description: The Salt Cycle Process is a nuclear fuel processing approach designed for application in compact facilities located at the reactor sites. Irradiated UO/sub 2/ fuels would be processed through a brief sequence of steps and partially purified UO/sub 2/ or UO/sub 2/--PuO/sub 2/ powders recovered, suitable for refabrication into fuel elements. The major steps of the process are the dissolution of uranium oxides in molten NaCl--KCl eutectic by chlorination to form soluble uranyl chloride and the red… more
Date: August 1, 1960
Creator: Benedict, G.E.; Lyon, W.L.; Mudge, L.K.; Swanson, J.L. & Walling, M.T. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THE IMPACT PROPERTIES OF UNALLOYED PLUTONIUM

Description: The effect of temperature on the unnotched and notched Charpy impact properties of plutonium was studied in the alpha, beta, gamma, and delta phases encompassing a temperature range of -43 to 330 deg C. Impact energies for unnotched specimens generally increased with increasing test temperature in the alpha and beta phases. Brittle failures were obtained in these phases. The specimen tested in the gamma phase did not fracture but bcnt in ofi U-shape and pulled through the anvil. lmpact energies… more
Date: October 1, 1961
Creator: Gardner, H.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Laboratory Investigation of Decontaminating Solutions for Primary Loop Decontamination in the New Production Reactor

Description: An investigation was made of methods for decontaminating the primary loop of the New Production Reactor (NPR). Decontamination factors ranging from fifty to several thousand were obtained with several different combinations of cleaning solutions. In general, fission product activity was removed to a lower residual level than was activated corrosion product activity, and carbon steel was easier to decontaminate than was stainless steel. It was necessary to completely remove the oxide film from t… more
Date: November 1, 1960
Creator: Mendel, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Recovery and Purification of Multi-Kilocurie Quantities of Fission Product Strontium by Cation Exchange

Description: In seven production runs, 75,000 curies of Sr/sup 90/ were isolated and purified in the ion-exchange equipment of Hanford Laboratories High Level Cells. The production goal (60,000 curies of purified Sr/sup 90/) and the time schedule were met or exceeded and the product exceeded the customer's purity requirements. The hot-cell-purified strontium made possible the completion on time of the Weather Bureau power source and the Martin 10 watt SNAP VII-A and VIl-C units. The isotopic purity of the s… more
Date: September 1, 1961
Creator: Bray, L. A.; Lust, L. F.; Moore, R. L.; Roberts, F. P.; Smith, F. M.; Van Tuyl, H. H. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

GRAIN REFINEMENT PRODUCED BY AN ALPHA PHASE ANNEAL OF BETA PHASE HEAT TREATED AND WATER QUENCHED URANIUM

Description: During an experiment involving alpha phase annealing (at 610 to 655 deg C for 5 and 10 min) of beta-quenched uranium, it was determined that the relatively coarse, irregular shaped grains (0.08 to 0.150 mm in diameter) in the beta-quenched structure, were replaced by fine equiaxed grains (0.04 to 0.09 mm in diameter). (auth)
Date: January 1, 1955
Creator: Gardner, H.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PLUTONIUM OXALATE DISK FILTER AND FILTER MEDIA STUDIES

Description: for filtration of plutonium oxalate slurries. A scalpel produces a slit in the filter precoat, leading to increased filtration in this slit, and the oxalate is removed by a doctor knife; this technique results in prolonged blowback cycles and more uniform delivery of filtered oxalate to subsequent processing steps. Several types of filter media were tested, and rigid porous aluminum oxide was found to be the best one. (D.L.C.)
Date: October 19, 1959
Creator: Rey, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Research and Development Activities Fixation of Radioactive Residues Quarterly Progress Report, July-September 1961

Description: Progress is reported on research and development work in pot calcination and radiant-heat spray calcination studies of synthetic Purex high-level wastes; and sorption studies using synthetic minerals and resins as well as natural minerals. The calcination studies are discussed in terms of batch calcination, melting of pot calcination products, spray calcination, and off-gas treatment; and sorption studies in terms of mineral reactions, fixation chemistry, and condensate wastes. (B.O.G.)
Date: October 13, 1961
Creator: Irish, E.R. ed.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DEMONSTRATION OF AN IRRADIATED UO$sub 2$ FUEL RECYCLE: FIRST RECYCLE

Description: Irradiated UO/sub 2/ was processed for recycle by one version of the Salt Cycle Process. The irradiated fuel was dissolved in fused NaCl-KCl and the bulk of the uranium and plutonium were recovered as UO/sub 2/ and PuO/sub 2/ by elcctrodeposition. A reduction in the concentration of fission product poisons in the fuel was also achieved in the electrodeposition step. Fabrication of the partially decontaminated, irradiated UO/sub 2/ into a fuel rod and subsequent incorporation of the fuel rod int… more
Date: September 1, 1961
Creator: Swanson, J L; Benedict, G E; Smith, R C & Horn, G R
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Research and Development Activities Fixation of Radioactive Residues, Quarterly Progress Report, October-December 1961

Description: Resesrch and development activities in fixation of radioactive wastes are reported. Spray calcination, batch calcination, in-tank solidification, off- gas treatment, sorption snd extraction studies, low- and intermediate-level wastes, and high-level wastes are discussed. (M.C.G.)
Date: January 15, 1962
Creator: Irish, E.R. ed.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experimental Evaluation of the Combustion Hazard to the Experimental Gas- Cooled Reactor-Preliminary Burning Rig Experiments

Description: >An assembly was constructed which simulated the moderator coolant annulus in the Experimental Gas-Cooled Reactor. This assembly was preheated to various temperatures and air was passed through the coolant annulus. Under certain conditions it was demonstrated that self-sustained combustion of the graphite could occur. Rates of temperature rise were generally less than 1 deg C/ min until the graphite temperature exceeded 700 deg C and then rise rates became very high. In these cxperimcnts, the a… more
Date: November 1, 1961
Creator: Dahl, R.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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RADIATION EFFECTS IN GRAPHITE

Description: A review of radiation effects on graphite is presented. Included are discussions of the general relations of these effects with original structural properties, and details of radioinduced changes. Other discussions are devoted to stored energy, annealing, and future problems in the use of nuclear graphite. Data and illustrations concerning structure and radioinduced changes are included. (J.R.D.)
Date: May 11, 1962
Creator: Nightingale, R.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THE HEAT TREATMENT OF PLUTONIUM

Description: Two groups of plutonium bars, one group containing 165 ppm iron and the other 678 ppm iron were end-quenched from the beta, gamma, delta, delta-prime, and epsilon phases. In general, cooling rate was found to have three striking effects on microstructure. The alpha grain size was found to decrease with increasing cooling rate during cooling from all phases. Upon cooling high-iron plutonium from the epsilon phase, the size of the Pu--Pu6/sub 6/Fe eutectic network decreased with increasing coolin… more
Date: February 1, 1961
Creator: Gardner, H.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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LIMITATIONS FOR EXISTING STORAGE TANKS FOR RADIOACTIVE WASTES FROM SEPARATIONS PLANTS

Description: The physical limitations of existing storage tanks for radioactive wastes from separations plants are defined as a guide for preparing process and operating criteria for the existing tank forms to assure continued integrity of the tanks. A "safe-load" curve for each of the four groups of tanks based on current technology is presented. Loading conditions, operation procedures, and thermal stresses are discussed. (M.C.G.)
Date: October 22, 1959
Creator: Doud, E. & Stivers, H.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Transformation Kinetics of Plutonium. Part Iii

Description: Isothermal reaction curves and T-T-T curves showing the effect of different variables on the beta-alpha transformations in plutonium are presented. Impurity content, stresses, beta heat-treating time and temperature, hydrostatic pressing, specimen size, and thermal cycling influenced the kinetics of the beta- alpha transformation. Decreasing the impurlty content increased the rate of transformation. High tensile stress retarded the beta-alpha transformation. Increasing the beta heat-treating ti… more
Date: December 1, 1961
Creator: Nelson, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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