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Injection Trajectories and Beam Matching for the Cambridge Electron Accelerator: "ABS>Injection trajectories were calculated for different injection conditions for the Cambridge Electron Accelerator, considering also the effect of magnetic fringing fields. The general problem of matching the emittance of the linac to the acceptance of the synchrotron in the transversal phase space is considered, and it is shown that this can be done by a set of two quadrupole lenses. In order to eliminate rudial betatron oscillations due to energy deviations of the injected particles, a pulsed electric quadrupole lens in the synchrotron in combination with two deflectors between linac and synchrotron can be used to place particles of different energies on their specific equilibrium orbits. A layout of the whole injection system following the output of the linac is given."
Precision Beta-Ray Spectroscopy : Termination Report: Detailed information on the radiations associated with several even-even isotopes has been obtained. In some instances enough information has been gathered to allow construction of skeleton energy level diagrams for the isotopes. Activities studied were obtained from pile irradiation of pure odd-even natural isotopes and included Dy160, W182, Sm152, Gd152 and Gd154. Details of the work done on and results obtained for these isotopes are reported in section 3. Some analytic and experimental studies were carried out on the application of tilting beta-ray spectrograph sources for improvement of resolution. The uses and limitation of this technique are discussed in section 2.
Instantaneous Velocity Profile Measurement by Photography: The following is taken from ORNL-2257, Instantaneous Velocity Profile Measurement by Photography, by R. E. Lynch, L. D. Palmer, and G. M. Winn. This report is in in preparation status; and errors, inconsistances, and omissions in he language, as well as in the technical aspects, may exist. The technique of using phosphorescent particles to enable photographic determination of qualitative and quantitative instantaneous velocity profiles is covered by AEC Patent Application No. SN-710, 371 issued to F. E. Lynch, L. D. Palmer, H. F. Poppendiek, and G. M. Winn and entitled " A Method of and Means for Visualizing Fluid Flow Patterns.
Status and Future Program of Homogeneous Reactor Fuel Processing Studies: The behavior of insoluble corrosion products in the HRT is generally understood and studies of the removal of these solids by hydroclones can logically be terminated after the effect of higher processing rates by the multiple hydroclone has been determined. Chemical descaling may be required to supplement solids removal by hydroclones. Laboratory studies to find suitable reagents will be continued in conjunction with decontamination work presently in progress.
Power Distribution of Tower Shielding Facility Reactor (TSR): The horizontal and vertical power distribution for a 5 x 7 fuel element loading of the TSR is presented. (auth)
HRT Temperature Measurement System - Issue No. 3: The following temperature measurement tabulation consists of two parts. Part I lists all HRT thermocouples, their location, the junction box thru which the leads pass, and their termination, if on an instrument. Part II lists all temperature read out instruments and their location. A total of 577 thermocouples are listed in this tabulation. The roughly 77,000 ft of wire used in connecting them up cost $6,799. Temperatures are read on 24 instruments. Cost of these was approximately $15,688. Accessories such as patch panels, conduit, disconnects, etc., used in installing the thermocouples cost about $8,069. Total cost for material and instruments for temperature measure comes to approximately $30,556.
The Alkaline Method for Treatment of High Radiation Level Aluminum Wastes: The method is based on caustic precipitation and centrifugation (which removes the Cs and small amounts of Sr, rare earths, Zr, Nb, and Ru). These are removed in the supernatant and run through a cation exchange column. This separates Zr-NB and Ru. The effluent is precipitated and the Zr-Nb is stored in an asphalt pit. The Ru then may be recovered from the precipitate. The precipitate from the original centrifugation is calcined, pressed and transported to a deep well.
Estimation of the Thermal Conductivity and the Viscosity of Gases at High Pressure: Few data exist for the thermal conductivity and viscosity of gases at very high pressure. The possibility of using gases for heat transfer media at pressures up to 100 atmospheres and above raised the problem of estimating variations in the conductivity and viscosity at high pressure. Generalized plots are presented which are based on the work of Enskog, Eucken, and Hirschfelder et al. Some pertinent data from Hirschfelder et al and from Hilsenrath et al are presented.
Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report April 1, 1962 - July 31, 1962: This report covers the S-I-5-B-M fuel irradiation in the GETR Maritime Loop during the final quarter of fiscal year 1962 plus the month of July 1962 to conclude the irradiation program. The data are summarized in Section II.
Preparation of Plutonium Sheet by Extrusion: Plutonium sheet of uniform thickness and good surface can be made by the extrusion of a tube which is then split and flattened. This report describes the equipment and the operating conditions for making sheet 0.005 to 0.055 in. thick with areas up to 24 in. square.
Air Scattering of Co60 Gamma Rays: Theory Versus Experiment: For Co60 source at 15 meters, the air-scattered gamma dose rate predicted by theory is excerpted from ORNL-1575, pp. 167-203. This is compared with experimental measurements for the same source and comparable geometry reported by Convair in CVAC-170T. After applying an appropriate correction for ground scattering as estimated in Mart-55-16T (Convair), the two results are found to be in substantial agreement.
Development of the Excer Process: Two revised Excer process flowsheets are presented for the production of UF4 from urnayl nitrate solution. In both, the uranium is sorbed on a cation-exchange resin and eluted with aqueous HF. In one, the resulting UO2F2 in dilute HF is mixed with dilute sulfuric or hydrochloric acid and electrolytically reduced in a cation-exchange-membrane cell, and the precipitated UF4·0.75H2O is dried and dehydrated to anhydrous UF4. A cost of 20¢ per pound of reduced uranium is estimated. In the other, ammonium fluoride is also added to the uranyl fluoride solution before the electrolytic reduction step, and the precipitate is UF4·04NH4F. A flowsheet for preparing UF4 from raw ore is also shown. The uranium is sorbed on an anion-exchange resin from a sulfuric acid leach liquor and eluted with dilute HCl. Ammonium fluoride and HF are added to the UO2Cl2-HCl solution before the uranyl ion is electrolytically reduced to precipitate UF4·0.4NH4F. Decontamination factors as high as 45 and 9 for gross beta and gamma activities and of 10 to 5000 for light metal impurities were obtained in the electrolytic reduction step.
The Isolation and Purification of Americium: Gram amounts of americium were separated quantitatively from kilogram quantities of lanthanum to yield an americium product approaching 90% purity. The remaining impurity was chiefly yttrium. Elution of americium from 25% loaded Dowex 50 resin column with 0.15 M citric acid— 0.10 M diammonium citrate — 0.3 M ammonium nitrate, pH 3.3 gave a product containing 99% of the americium with a La/Am ratio of 1/100 or less in one fourth of a column volume, in this case about 1 100-fold volume reduction. Approximately 9 g of americium was purified by this method. Elution with 12.8 M hydrochloric acid from a 20 to 30% loaded column gave 90% of the americium in two column volumes of product with a La/Am ratio of about 1/4. About 1 g of americium was purified by this method.
Digital-to-Analogue Converter (Punched Tape to X-Y Plotter): A digital-to-analog converter is described which is a part of a system that converts punched-tape digital data to analog data in a series of points drawn by an x-y plotter. The converter is designed to plot accurately tapes that contain information other than coded numerical coordinates. Operation of the converter is also described along with format requirements and power supplies. (J.R.D.)
Steam Water Pressure Drop and Critical Discharge Flow - A Digital Computer Program: It is the purpose of this report to explain the bands and uses of a digital computer program for the calculation of steady state steam-water pressure drop and critical flow in pipes. The program has been coded for the IBM 709 computer. While so attempt has been made to obtain improved models of two-phase flow, it is believed that the numerical integration technique used in the code will permit more accurate calculation where pressure drops are large compared to the upstream pressure. The technique should lend itself readily to any improved correlations which appear in the future.
Reamed Rear Face Parker Fitting: A study and tests of the feasibility and best method of reaming rear face Parker fittings has been made. Flow increase of 8 percent, based on maintaining the same front header pressure, can be obtained at B, D, and F reactors by reaming the rear Parker fittings to .610 inch and using existing rear face hardware. Tests indicate mechanical strength will not be significantly reduced, high frequency vibration will not be increased, and that methods of reaming are available.
"Crud" Scrubbing with a Purex-Type Zebra Cartridge: Entrained solids have in the past been one of the major factors limiting solvent extraction fission product decontamination. These solids are known to be surface active, to absorb fission products, and to form interfacial films or "cruds". A major step in eliminating these cruds was taken when the Purex columns were modified to operate with the interfaces at the waste ends of the columns rather than the product ends. This type of operation tended to flush the solids out with the waste rather than the product streams.
Quarterly Report Technology of Non-Production Reactor Fuels Reprocessing Budget Activity 2790: This report summarizes the research and development work carried out during June, July, and August, 1959, for Budget Activity 2790- Separations Development for Non-Production Reactors. The effort on Activity 2790 - Separations Development for Non-Production Reactors. The effort on Activity 2790 will enable Hanford to begin reprocessing in January, 1962, the fuel elements from power reactors which employ depleted or slightly enriched uranium fuels.
Division of Reactor Development Programs Monthly Report- July 1959: Basic Studies. Sinterability studies on the isomorphous system UO2-PuO2 have continued. One-half inch diameter X 3/8'' long compacts containing physical mixtures of the two components have been heated in hydrogen. Sintered density as a function of time and temperature has been determined for times of one and eight hours up to 1600 C. In general, there seems to be minima on isothermal plots of density versus composition in the intermediate range 20-40 w/o PuO2. At concentrations greater than 40 w/o PuO2, density increases rapidly with increasing PuO2. In every case pure PuO2, (produced by decomposing plutonium oxalate at at 300 C) sintered to a greater density that ball ball milled PWR grade UO2. The data, for a one hour soak time, and tabulated in percent of the theoretical crystallographic density, can be seen below:
Plant Modification for Reprocessing Non-Production Reactor Fuels Design Criteria for Fuel Element Storage Facility Building 221-U: Facilities shall be provided in the 221-U Building for removing fuel elements from the casks as placed in the railroad tunnel from the transfer facility and moving the elements to modified existing 10' X 16' X 14' storage tanks in ten existing cells where they will be stored, until scheduled for processing.
Quarterly Report - October, November, December 1958 Plutonium Fuels Development Plutonium Metallurgy Operation: A number of Pu-Al and UO2-PuO2 Zircaloy clad capsules have been fabricated for irradiation in the MTR. In addition, a four rod cluster containing Al 8 w/o Pu and Al 12 w/o Si 8 w/o Pu cores has been successfully irradiated and discharged from Loop 3 of the KER. A second four rod cluster is awaiting irradiation and design and fabrication of a seven rod cluster test element is underway.
Program on the IBM 709 Digital Computer of the P3 Approximation to the Boltzmann Transports equation in Cylindrical Geometry: In formulating this general diffusion theory expression which represents the neutron balance in a nuclear chain reactor the following assumptions were made : (1) the medium through which the neutrons are diffusing has a low neutron capture cross section, (2) the region in which the flux distribute is being described is two or three mean free paths from strong sources and sinks or from a boundary. Certainly, is going to the lattice cell of a receptor, both of the above conditions are violated; fuel elements have a large absorption cross section and most lattice cells are only two or three mean free paths to is over-all sites
Fluorescent X-Ray Spectrography- A Recent Analytical Technique: Because of the relative simplicity of the X-Ray spectra and recent improvements in instrumentation, analytical applications of X-Ray of spectrography are becoming very popular. The method us applicable to both qualitative and quantitative determinations of all elements heavier than sodium. Elements in multicomponent systems, such as alloys and minerals, and elements such as, W, Pt, Nb, Ta, Hf, Zr, and the rare earths, which are difficult to separate or determine by other methods, can usually be determined directly without special sample treatment. The method is rapid and precision is comparable to wet chemical analyses. It is applicable over the very wide concentration range from parts per 10,000 to 100 percent, and can be applied to the analysis of all kinds of samples- metals, drillings and thin films, powders, glasses, or liquids. The method is described and its advantages and limitations are discussed. Typical analyses are mentioned and sensitivity limits for determination of the various elements are illustrated as a guide to possible uses of X-ray spectrography.
The Distributions in Energy and in Number of Electrons and Photons in Cascade: Derived With Energy-Dependent Bremsstrahlung, Materialization, Collision Loss and Multiple Scattering: Diffusion equations for a cascade shower which include an energy cutoff and energy parameters for each particle have not previously been studied. In this paper it is found that an inclusion of both permits collision loss to be represented as a discrete process by modifying the differential radiation cross section.
Energy Spectrum of 320 Mev Deuterons From He3: The previous calculation of the energy spectrum of the high energy deuteron beam from the stripping of He3 (UCRL-2150) was thought to be in error, especially as regards the low energy tail, on the basis of some experiments with the neutron time-of-flight detector, which indicated a considerably narrower spectrum than that calculated in UCRL-2150. Since the value used for the attenuation cross section of deuterons in uranium is considerably lower than that presently considered correct a new calculation was made using this latter cross section. Since the equations used in this new calculation differ somewhat from those used in the previous report a brief derivation is given here.
MTA, A-12 Development, Drift Tubes - RF and Beam Geometry. Comparison of A-12 to A-24: The final r.f. characteristics of A-12 are shown. The mechanical features are available in UCRL-1859. If A-12 were to be changed to 24.2 mm rather than 12.1 mm, keeping the same length and the same constant average coil gradient of 0.375 MV/ft., the characteristics of such an A-24 can be obtained from the attached curves.
Sheet Metal Can Furnace: A need for a small vertical cylinder-type furnace arises frequently in the Chemistry Department at the Lawrence Radiation Laboratory (LRL). Adequate heat is the major requirement; close control or calibration is not usually necessary. A heating unit of this type can either be used for quickly concentrating solutions in centrifuge cones or, by the addition of a refractory pedestal--can be made into a crucible furnace for size 0 and 00 crucibles. Because much of the chemistry done at LRL is with radioisotopes, disposal of contaminated equipment is an important consideration. In general, furnaces are difficult to decontaminate, hence there was a need for a disposable type. Because nothing meeting the requirements seemed to be commercially available, the Health Chemistry Department made up a simple furnace that has proved useful.
Fabricating Liquid-Hydrogen Targets From Mylar: The increasing popularity of liquid-hydrogen targets in physics research has emphasized the need for containers with maximum beam transparency (i.e., thin walls and low Z) and suitable strength at cryogenic temperatures. Fabrication of a Mylar container satisfying these requirements is described here.
Close-Capture Adsorption System For Remote Radioisotope Chemistry: Molecular sieves are synthetic zeolites which, when dehydrated, contain a network of empty pores and cavities that constitute almost 50% of the total volume of the crystals. They have the unique property of adsorbing within these cavities only those molecules that are small enough to pass through the pores of the crystals, Molecular sieves have a very strong affinity for water and other polar molecules. It is this selective property plus their stability and reasonable cost that make them of interest for the application described herein.
Decay-Energy Systematics Of The Heavy Elements: Figures 1 and 2 summarize total decay energies for the four radioactive series. The alpha-decay energy obtained by measuring the energy of the alpha particle leading to the ground state includes the energy of the recoil nucleus. The curve shown in figure 3 defines in broad outline the conditions and regions of alpha instability. A great deal more is to be learned from a more detailed examination of the region where alpha radioactivity is prominent. Of great value to the experimentalist is that he is able to predict alpha energies, and the agreement between predicted and measured values often serves as a criterion for isotopic assignment. A number of systems for correlating alpha decay energies have been employed, and that perhaps most widely used is illustrated in figure 4. Here the isotopes of each element on a mass number vs. energy plot are joined, resulting in a family of curves which over a wide region comprise a series of nearly parallel lines.
Current-Switching Circuitry: This paper discusses a group of high-speed switching circuits using the basic current-switching mode of operation. The first part of the paper presents a dynamic analysis of the basic current-switching mode and the second part is the dynamic and steady-state analysis of a current-switching flip-flop.
Radioactivity Levels of the Columbia River Below Richland, Washington for the Period April, May, June 1956: In the Columbia River downstream from Richland, Washington there is a gradual decrease in concentration of radioactive isotope. At any one location there are fluctuations due to factors such as dilution and decay time. During this period at all locations the concentration of alpha particle emitters in water averaged below the detection limit. Beta particle emitters in water upstream of McNary Dam decreased slightly due to increased river flow this quarter, with averages at various locations. Downstream from McNary Dam, beta particle emitter average concentrations in water were about the same as the past three quarters.
The Creep of Zircaloy-2 Process Tubes: The creep problems associated with zircaloy-2 process tubes and the factors affecting the creep of these tubes were discussed in detail. Emphasis was placed on the determination of the tube wall thickness for an SPR tube, whose minimum thickness is limited by creep considerations. It was concluded that, at the present time, there is not enough information available to design zircaloy-2 process tubes on a realistic basis. Various experiments were suggested to supplement the creep rate testing program being pursued by Battelle Memorial Institute.
Reduction off Plutonium (VI) with Hydrogen Peroxides: Hydrogen peroxide has been used to reduce plutonium (VI) in nitric acid solution to the (IV) valence state. However, reduction of plutonium (VI) solutions containing iron has often been incomplete when hydrogen peroxide was used as the reducing agent. Since reduction of plutonium (VI) has been applied in plant solutions containing iron, a study of the plutonium (VI) reduction with hydrogen peroxide was undertaken. Variables tested included plutonium, nitric acid, and iron concentrations.
Analysis of the Zircaloy-2 Creep Data with Two Extrapolation Methods: The experimental evaluation of low (10⁻⁸ in/in/hr) creep rates are costly and time consuming. Thus, in answer to a request from the design group, the creep data on Zircaloy-2 obtained at Battelle Memorial Institute is extrapolated into the low creep rate range. Because the methods of extrapolation have not been evaluated at very low creep rates on Zircaloy, two different methods are used to analyze the creep data. The methods of extrapolation are given so that future analyses can be carried out by the design group or by other sections interested in predicting creep rates which have not been experimentally determined.
A Kinetic Study of the Fluoride Catalyzed Nitric Acid Dissolution of Thorium Metal: The penetration rates of thorium metal by boiling nitric acid were measured as a function of the concentration of fluoride catalyst and of nitric acid. Dissolved thorium and aluminum were found to inhibit the reaction. Thoris exhibited penetration rates much lower than those of thorium metal. In addition to the specific rate measurements, pot type batch dissolvings were carried out to estimate plant time cycles. An empirical mathematical equation was devised which correlates the results of these batch dissolvings and facilitates application of the data to other types of dissolvers.
{{{title}}} metadc1254011: The absorption of the important fission products by plants is quantitatively presented as a concentration factor which is defined as the ratio of the fission product concentration found in the leaves to the fission product concentration found in the nutrient substrate. Of the fission products, the isotopes of strontium were found to be the most important by virtue of their high concentration factor, long half-life, and low maximum permissible amounts for animals. Iodine and barium follow in importance, with cesium moderately important in some soils. All other fission products have concentration factors less than strontium by 100 or more. The effect on the concentration factor of different agricultural plants, as well as different organs of the same plant, causes variations of about a factor of ten or less for each isotope. The concentration factor tends to increase as the pH of the nutrient substrate is decreased. Addition of stable carrier to the substrate does not decrease the amount of the radioactive isotope that is absorbed into the plant. The presence of iodine and yttrium carrier actually causes a significant increase in the concentration of the respective radioactive isotopes in the plant tissue.
Calcium Uranium(IV) Fluoride; Precipitation and Reduction to Metal: Using ferrous ion in the presence of fluoride for reducing uranium(VI) to the four state, the salt calcium uranium (IV) fluoride can be precipitated from uranyl nitrate solutions. X-ray studies have shown that the precipitate is a true double salt and not a mixture of the two insoluble fluorides of calcium and uranium. The salt settles rapidly and can be either filtered or centrifuged. Waste losses during precipitation and washing were on the order of 2.0 and 0.4 per cent, respectively. These waste losses are not primarily solubility losses. During filtration of the supernates some fines were not removed by the sintered glass filter, and post-precipitation was also noticed. The hydrated salt contains approximately one mole of water which can also be removed without hydrolysis by drying at 250 C in an atmosphere of deoxygenated argon. Dry calcium uranium fluoride prepared in this manner is free flowing with a bulk density of about 1.25 g/cm³.
Proposed Clean-Up System for Carbon Steel High Temperature Recirculation System: It is the purpose of this document to outline a proposed addition to the previously considered clean-up systems as a possible solution for the maintenance of high purity water. A cyclone separator system has been devised in conjunction with the water clean-up of a high temperature recirculating reactor cooling system. By utilizing such a cyclone separator system, a high quality water can be obtained in a primary coolant system made up of carbon steel components without excessive clean-up costs.
The Aeolotropic Elastic Relations for Uranium Crystals: Handwritten report. This theoretical introduction to the anisotropic elastic properties of the orthorombic [sic] uranium crystal presents certain basic ideas which are useful in the study of experimental methods for determining preferred orientations in polycrystalline bodies. The method of analysis used to determine the elastic constants suggests explanations and correlations for the observations of sonic wave experiments on bars having preferred orientations and also serves as an introduction into the type of mathematical relations used in the study of anisotropic crystals.
The Proton-Proton Triple Scattering Parameters R and A at 213 Mev: "As a part of a program to determine the p-p scattering matrix at 213 Mev, the triple scattering parameters R and A were measured at 30, 40, 50, 60, 70, 80. and 90 deg in the center-of-msss system. The results are compared with a phase shift analysis by MacGregor and Moravcsik and with the predictions of the boundary condition model of Saylor, Bryan and Marshak."
Comparison of Radiation-Induced Graft Copolymerization Untilizing Electron Accelerators and Isotope Sources as Radiation Initiators: "A brief examination of the post irradiation grafting of machine irradiated polyethylene film with acrylic acid monomer was made. Evidence of postgrafting was detected in samples that had been irradiated to a total dose of 10 Mrads at a dose rate of 0.01 Mrad/sec. and then exposed to a 25% purified acrylic acid solution in benzene for periods of 1 to 4 days."
Warping Instability in Long Rods: Abstract. If a pile rod gets bowed within its cooling tube it becomes warmer on the side which approaches the tube wall, and thermal expansion tends to warp it in the same direction as the original displacement. This was discussed roughly in N-601, and it was there concluded that the mechanism was not important for an isolated short slug. In connection with current development of continuous jacket (cartridge) assemblies, it seems desirable to look at this question again. In this case it is possible that the effect may be of some concern.
Resonance Absorption in Lumps and Mixtures: The resonance absorption of a lump is described in terms of three components. Calculations of resonance absorption are carried out using the model for the resonance spectrum of uranium recently derived; calculations are also made with variations of this model which involve local fluctuations in level strengths. For metal and oxide lumps the agreement with observation is satisfactory. For dilute mixtures, whose resonance activation was measured by Mitchell, computed values fall 20% to 30% above measured ones.
The Thermal Expansion of Five Titanium Carbide Cermets from 68 to 1800F: This technical report presents measurements of the thermal expansion of five titanium carbide type cermets from 68 to 1800F. These cermets are designated by Kennametal, Inc., as K 138A, K 150A, K 152B and K 162B. They contain from 64 to 80 weight percent titanium carbide, 10 to 30 weight percent metal binder and 6 to 10 weight percent other carbides. The metal binders are cobalt, nickel, and nickel and molybdenum. An attempt was made to calculate the thermal expansion of each type cermet from thermal expansions of the constituents. The expansion of the mixture was computed by weighting and expansions of the constituents according to (1) weight percent of the constituents, (2) volume percent of the constituents and (3) according to a value developed for mixtures by P. S. Turner. It was found that expansions computed according to volume percent and by Turner's method agreed with measured values with +- 5 percent. The values calculated by weight percent were from 5 to 11 percent higher than the observed values. The thermal expansions of these cermets are compared with the expansions of a group of metals and alloys.
Bonding of Tantalum: Technical report describing the investigation undertaken to determine the necessary requirements for obtaining sound bonded joints on tantalum. Corrosion and Mass Transfer Loops LTTN 237A and 427 called for fabrication of 430 stainless steel clad tantalum tubing. Since there was little or no experience at welding this material at CANEL, specimens were welded using vacuum chambers and plastic chambers as normally used for loop fabrication. Resistance welding was performed without the use of a special atmosphere producing sound bonds.
Ames Project, Chemical Research - General Chemistry, Report for the Period of April 10 to May 10, 1944: Technical report. Areas covered are properties of uranium halides, properties of uranium nitrides, and hydride formation at high pressure.
Zrclad Zirconium-Uranium Alloy Rod for Heat Thru-Put Test: The purpose of this work was (1) to investigate the possibility of producing zirconium-clad zirconium-uranium alloy objects by casting the core alloy directly into zirconium and zirconium-3 w/o tin jackets, producing a diffusion bond at the jacket-core interfaces, and (2) to produce small scale heat thru-put test specimens by this method.
The Manufacture of Aluminum Clad Aluminum-Plutonium Alloy Irradiation Specimens: This report describes the manufacture of 25 Aluminum clad, 10 w/o plutonium-aluminum alloy and 5 w/o plutonium-aluminum alloy cored specimens for Argonne National Laboratory-University of California irradiation tests in the Materials Testing Reactor. The manufacturing method: preparation of cores and cladding material, assembly and welding of compacts, outgassing, roll bonding, shearing, identification marking and final fabrication into napkin "rings" is described in detail. Of ninety-six specimens fabricated, ninety-one were completed as finished specimens. Forty-four of these contained 5 w/o plutonium alloy cores and forty-seven contained 10 w/o plutonium alloy cores. Five specimens ere rejected for bond blistering.
A High Volume Casting Furnace for Plutonium: A high-vacuum casting furnace with an internal diameter of 15 inches has been designed, fabricated, and installed at LASL. The furnace was designed to accommodate casting crucibles up to 7 inches OD; however with a larger diameter heating element, casting crucibles up to 9 inches could be accommodated. This report describes the basic features of the furnace and presents engineering drawings of both the furnace and the furnace box.

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