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- Feasibility Study, Optimum Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission, Idaho Operations Office
- Report containing "a discussion of the feasibility design and cost estimates for a gas cooled, natural uranium, graphite moderated power plant optimized for minimum power cost" (p. 3).
- Feasibility Study, Optimum Partially Enriched Uranium, Gas Cooled, Graphite Moderated for United States Atomic Energy Commission, Idaho Operations Office
- Report that contains "a preliminary design and feasibility studies of gas cooled, graphite moderated, nuclear power plants" (p. 1).
- Liquid Thermal Diffusion
- This volume is one set of a series which has been prepared as a record of the research work done under the Manhattan Project and the Atomic Energy Commission.
- THE HEATS OF FORMATION OF URANIUM HYDRIDE, URANIUM DEUTERIDE, AND URANIUM TRITIDE AT 25 C
- No Description Available.
- Low Temperature Distillation of Hydrogen Isotopes
- No Description Available.
- Reactions yielding volatile oxides at high temperatures free energies of gaseous Al$sub 2$O, ZrO, ThO, TaO, ZrO$sub 2$, ThO$sub 2$, TaO$sub 2$, UO$sub 2$, and WO$sub 3$
- Although the oxides such as Al/sub 2/O/sub 3/, MgO, UO/sub 2/, ThO/sub 2/ , Be O, and ZrO/sub 2/ are used as refractory materials, very little reliable thermodynamic data predicting the stabilities of the gases in equilibrium with the solids at temperatures above 1700 deg C exist. In most cases the vapor pressures are not accurately known and in some cases the gaseous molecules are uncertain. Hence one experiences difficulties in attempting to predict ihe interaction of these oxides with the refractory metals such as tungsten and tantalum. The problems are made even more difficult because of a lack of reliable information concenning the gaseous oxides of tungsten and tantalum. As a means towards establishing the thermodynamic stabilities of these refractory oxides, the authors propose to survey the existing results and to describe some rather crucial experiments relating to the interaction of these oxides with tungsten and tantalum. Although not establishing accurate free energies, these experiments, neventheless, hnve shown conclusively the unreliability of some supposedly accurate thermodynamic properties because of a failure to examine the investigations in this manner. In addition, they indicate more reliable limits of free energies in certain cases. (auth)
- Van Slyke Factors for Hydrogen, Oxygen, Carbon Dioxide, and Carbon Monoxide
- Tables of data calculated on an IBM 610 automatic computer are given to convert the measured pressure differences in the Van Slyke gas analysis apparatus into micromolar concentration of gas in solution for hydrogen, oxygen, carbon dioxide and carbon monoxide in water. Measured solubility coefficients for carbon dioxide in various aqueous solutions of formic acid are given together with the conversion factors for use with the Van Slyke analysis apparatus. (auth)
- TEMPERATURE DEPENDENCE OF TAFEL SLOPE IN THE FORMATION OF VERY THIN ANODIC OXIDE FILMS ON NIOBIUM
- A kinetic study was made of the formation of very thin anodic oxide films on niobium at constant current over the temperature range --10 to 70 deg C. Formation voltages were limited to the range below the oxygen evolution potential to eliminate possible interaction of an electronic component of the current with the measured formation field. It was found that the measured temperature dependence of Tafel slope agreed with that predicted by the theory of Mott and Cabrera. Using this theory, a zero field interfacial barrier height of 1.19 ev and a half-jump distance of 2.40 A were obtained. Values of the differential formation field are reported at current densities of 1000, 100, 10, and 1 mu a/ cm/sup 2/ at ten degree intervals over the temperature range studied. (auth)
- STUDIES ON THE ANODIC POLARIZATION OF ZIRCONIUM--GROWTH RATES AND THICKNESSES OF THE VERY THIN ANODIC OXIDE FILMS
- No Description Available.
- The Uranium of the Lavas of Lassen Volcanic National Park, California
- No Description Available.
- Extraction of Uranium, Magnesium, Zirconium, and Cerium From Bismuth With a Fused Fluoride Salt Mixture
- The extraction of uranium, magnesium, cerium, zirconium, and niobium from bismuth with a molten mixture of sodium fluoride and zirconium fluoride was demonstrated. Comparative rates of extraction were obtained. The effects of high concentrations of magnesium and of hydrogen fluoride sparging on the extraction process were investigated. Tracer studies demonstrated that exchange occurs between zirconium dissolved in the bismuth and zirconium in the fused salt. The applicability of the fused fluoride extraction step to the processing of the Liquid Metal Fuel Reactor'' solution fuel is discussed. (auth)
- The Transfer of Plutonium Hexafluoride in the Vapor Phase
- Plutonium hexafluoride is decomposed by heat, by its alpha radiation, and by reactions with most materials of construction. Laboratory experiments were performed to investigate means by which plutonium losses due to these reactions can be minimized during vapor-phase transfers of the compound. The experiments showed that plutonium hexafluoride vapor could be transferred satisfactorily through well fluorinated nickel equipment in a stream of fluorine or helium. The decomposition product of plutonium hexafluoride was refluorinated at 250 deg C by fluorine. (auth)
- Estimate of the Probability and Consequences of Ignition of the HRT Charcoal Beds
- BS>The igition temperature of Columbia G activated charcoal in a flowing oxygen stream was determined to be 290 deg C under conditions simulating the inlet of the HRT charcoal beds. Calculations of charcoal temperatures resulting from beta decay of adsorbed fission gases from the HRT indicate that this temperature will not be reached provided the reacter power does not exceed 10 Mw with an accompanying oxygen flow not exceeding 2 liters/min. At lower power levels higher oxygen flow may be tolerated. If, by a combination of circumstances, ignition of the charcoal should occur, it will be possible to extinguish the fire by stopping the oxygen flow. The down-stream propagation of the combustion front is slow enough to allow detection and corrective action to be taken before a serious situation occurs. (auth)
- FISSION GAS HOLDUP TESTS ON HRT CHARCOAL BEDS
- Fission gas holdup tests on the HRT charcoal beds under simulated operating conditions are complete. A radioactive tracer technique developed for use in laboratory absorption studies was utilized. The efficiency of the charcoal beds, in regard to holdup of fission gases, exceeds design specifications. On the basis of these tests, the charcoal beds should perform satisfactorily with the l#T operating at 10 Mw with a total oxygen flow of 3 liters/min. or at 5 Mw with a total oxygen flow of 3.5 liters/min., assuming that the maximum charcoal temperature in the first sections of the bed does not exceed 100 deg C and that the temperature in the 6 inch diameter section is in the 15 to 20 deg C range. (auth)
- Examination of Inconel-316 Stainless Steel-Sodium Pump Loops 4689-5 and 4689-6
- No Description Available.
- Study of Atmospheric Contamination in the Melt Plant Building
- No Description Available.
- REACTION OF NITROGEN WITH NIOBIUM
- Reaction rates of niobium with nitrogen were determined gravimetrically from 675. to 875 deg C with a recording microbalance and volumetrically from 1100 to 1600 deg C with a modified Sieverts apparatus. Diffusion coefficients and terminal solubilities were determined from 800 to 1600 deg C by the concentration- gradient technique. Tne reaction of nitrogen with niobium follows a parabolic rate law at 675 to 1600 deg C. The expression for the diffusion coefficient for nitrogen in niobium at 800 to 1600 deg C is given as well as the expression for the terminal solubility for nitrogen in niobium. (auth)
- REACTIONS IN THE NIOBIUM-HYDROGEN SYSTEM
- Equilibria in the niobium- hydrogen system were determined in the range 100 to 900- deg , 0.1 to 1000 mm of mercury hydrogen pressure, and hydrogen/ niobium atomic ratios of 0.01 to 0.85. X-ray measurements were obtainpd at 25 to 400 deg C at hydrogen/niobium ratios up to 0.54. The studies showed thnt a solid solution of hydrogen in niobium is produced throughout most of the system. A miscibility gap was found at low temperatures and pressures, with a critical point at about a temperature of 140 deg C, a hydrogen pressure of 0.01 mm of mercury, and a hydrogen/niobium ratio of 0.3. Sorption rates at 300 to 550 deg C wore initially linear. At higher temperatures, sorption rates were controlled by diffusion in the metal matrix. Diffusion coefficients at 600 to 700 deg C can be expressed by D = 0.0215 exp STA(-9370 plus or minus 600)/RT!. Desorption rates were lower than those predicted by diffusion. (auth)
- Pressure Induced Metallic Transitions in Insulators
- Experimental evidence that several ionic and molecular crystals become conductors in the metallic range at ~ 250,000 atm. is presented. For some the transition pressure is roughly defined. (T. R.H.)
- THE CURRICULUM OF THE OAK RIDGE SCHOOL OF REACTOR TECHNOLOGY
- No Description Available.
- HEAT RELEASE IN NUCLEAR REACTORS
- Discussions are included on energy sources and modes of local deposition of heat, fission fragment and BETA decay energy, neutron energy, energy release by BETA decay of activated nuclei, neutron flux distribution, gamma heating calculations, and integration of the gamma heating equation for simple cases. (M.H.R.)
- OPERATING INSTRUCTIONS FOR THE UNIVAC PROGRAM OCUSOL-A, A MODIFICATION OF THE EYEWASH PROGRAM
- No Description Available.
- Technical activities report heat, water, and mechanical studies
- The heat studies include: automatic time-delay relay for Panellit System; heating of fuel rods; installation of a thermocouple slug; effect of tube length and annulus on tube power; pressure drop film studies; full scale mock-up; flow tests; front to rear enrichment of B, D, and F piles; electrical analog studies; studies on thermal and biological shields; and recirculating system heat exchangers. Some of the topics discussed in the water studies section are: the 100-D flow laboratory; film formation test apparatus; can difference test; Calgon chemical purge for film removal; flow laboratory recirculating studies; slug jacket abrasion at high flow rates; sodium dichromate elimination tests; process water studies; and corrosion studies. The mechanical development studies sections includes the following subjects: Sphincter seal test; ball corrosion test; horizontal control rod conversion study; P-13 removal; chemical slug stripper; temperature monitoring of tube outlets; slug air weigher; slug damage; process tube replacement; crossheader improvement; water cooled test hole facility; 189-D test laboratory; creep in process tubes; charging and discharging machines; flapper nozzle assembly test; horizontal rod gland seal test; and horizontal rod mock-up test.
- Technical activities report: Mechanical development studies
- This monthly progress report covers activities in the following areas: pile control; shielding studies; process tube assembly; pile operating equipment; power recovery; pile piping; and test laboratory. A detailed discussion is given for each topic.
- Investigation at high subsonic speeds of finned and unfinned bodies mounted at various locations from the wings of unswept- and swept-wing--fuselage models, including measurements of body loads
- Report presenting an investigation to determine the effects of location of bodies (finned and unfinned) on the aerodynamic characteristics of unswept- and swept-wing--fuselage models and to determine the aerodynamic loads on the bodies in the presence of the wings. Results for the complete model characteristics and for the body are provided.
- Graphite burn-out resulting from carbon monoxide formation in C Pile
- With the introduction of carbon dioxide into the piles as a gas atmosphere, new problems arose which concerned the chemical reactions undergone by the pile graphite with the gas atmosphere. In the interest of obtaining a better understanding of the nature and extent of these graphite-gas reactions, mass spectrometer analyses of the pile gas from a selected sampling port at C Pile were initiated at the time of start-up of that unit and were continued until several steady state conditions had been observed. The results of these analyses are presented and discussed herein.
- PROGRESS REPORT ABNORMAL BLEEDING
- No Description Available.
- The Determination of Mesothorium in Thorium Nitrate
- No Description Available.
- Kinetics of the Los Alamos Power Reactor Experiment (LAPRE)
- A theoretical study of the kinetics of a model of the Los Alamos Power Reactor Experiment (LAPRE) was made through integration of the dynamic equations with the IBM 701 computer. The stability is investtgated under various conditions of power demand, rod-induced reactivity changes, and other conditions especially applicable to LAPRE. The results are given in graphical form, along with conclusions as to appropriate conditions of operation. (auth)
- The Transient Behavior of Single-Phase Natural Circulation Water Loop Systems
- No Description Available.
- Lifetime of K Mesons
- No Description Available.
- An Investigation of the Application of the Gas Generator-Free Turbine Cycle to a Nuclear Powered Aircraft
- This study has investigated the feasibility of installing a gas generator-free turbine type power plant in the R3Y aircraft, using a circulating fuel reactor as a power source. Two variations of the cycle were considered. The split flow cycle bleeds high temperature, high pressure air from the gas generator directly to the free turbine in the wing. The through flow cycle partially expands the high temperature, high pressure air through the compressor turbine of the gas generator then directs the compressor-turbine exhaust air to the free turbine in the wing. Design parameters of pressure ratio, radiator depth, radiation flow density, and hot gas duct size were optimized to give minimum weight per shaft horsepower of the complete power plant. The weight of a split flow power plant capable of supplying 22,000 shaft horsepower was found to be 116,600 pounds. The weight of a similar through flow power plant was found to be 119,900 pounds. The reactor power required in both cases was 70 megawatts. The nominal gross weight of the R3Y airplane is 175,000 pounds. With pay loads of approximately 20,000 pounds, either nuclear conversion will have a gross weight of 200,000 pounds. It was found that either cycle could be installed in the R3Y aircraft; however, the installation of either would require major structural redesign. The split flow cycle with its smaller hot air ducts required the least amount of redesign. A comparison of existing aircraft engines with a preliminary design of the split flow turbo-components indicated that the compressor and possibly the free turbine could be adapted from current engine components.
- On the Calculation of Properties of Gases at High Temperatures. Technical Report No. 2
- The role of the potential of intermolecular force in determining properties of gases at elevated temperatures is discussed. Coefficients of viscosity and selfdiffusion, isotopic reduced themaal diffusion ratios, and second virial cofficients for helium, argon, and nitrogen at 1,000, 5,000, and 15,000 d K were calculated from extrapolated potentials and from beam potentials. (W.D.M.)
- Semi-Annual Progress Report in Chemistry for the Period October 1,1950--March 31,1951
- Report discussing the progress made on various chemistry research projects at Ames Laboratory during the period from October 1, 1950 to March 31, 1951.
- DESIGN OF PROTECTIVE STRUCTURES (A NEW CONCEPT OF STRUCTURAL BEHAVIOR)
- No Description Available.
- PRELIMINARY REPORT OF FUSED SALT MIXTURE NO. 130 HEAT TRANSFER COEFFICIENT TEST
- Heat transfer data are presented over a Reyuolds Number range of 400 to 8000 for the test fused salt Mixture No. 130 (62 mol % LiF-37 mol % BeFi-1 mol % UF/sub 4/ for a calibrating used salt Mixture No. 30 (50 mol % NaF--46 mol % ZrF/ sub 4/--4 mol % UF/sub 4/) flowing inside round heat exchanger tubes. A prelima- nary equation is developed for predicting shell-side heat transfer coefficients for liquid metal in turbulent, longitudinal flow over a square tube array having a pitch/diameter ratio of 1.165. An experimental value of the specific heat of fused salt Mixture No. 130 is also determined from the test data. (auth)
- NON-PRODUCTION FUELS REPROCESSING, CENTRIFUGATION STUDIES ON VARIOUS DISSOLVER EFFLUENT SOLUTIONS
- >The proposed flowsheets for reprocessing of nonproduction fuels include centrifugal separation of particulate matter from various dissolver effluent solutions. The settling characteristics of process solids were determined in water and in cold process solutions. Uranium dioxide particles will be recovered from Zirflex and Sulfex cladding waste solutions, and core-dissolver solutions will be centrifuged for removal of ZrO/sub 2/, metallic slimes, siliceous matter, and uranium-bearing solids. (W.L.H.)
- PHYSICAL PROPERTIES OF NEUTRALIZED ZIRFLEX WASTE
- An investigation was made to determine the physical properties and flow characteristics of the neutralized slurry to assist in the selection of satisfactory transfer equipment and storage conditions. The neutralized Zirflex waste slurry contalns 20 vol.% rapidly settling solids. It can be transferred easily if the flow is in the turbulent condition, but agitation is needed during temporary storage. Pipe lines should be flushed with water after transfer of the waste slurry. (W.L.H.)
- Relationship Between Small Angle Dislocation Boundaries and Creep. Technical Report No. 15
- No Description Available.
- Quantitative Substructure and Tensile Property Investigations of Nickel Alloys. Technical Report No. 14
- No Description Available.
- OXIDATION OF CHLORIDE ION BY CERIUM(IV)
- No Description Available.
- Occurrence of Technetium in Nature : Final Report for the Period November 1, 1954 to August 31, 1955
- Twelve neutron activation analyses for naturally occurring technetium-98 were performed. Positive results were obtained in ten cases. Precautions were taken to avoid interference by molybdenum and technetium-99. the cross section for the reaction [formula] as found to be equal to 4 +- 2 mb for the neutron spectrum of the vertical thimbles of the Argonne CP-5 reactor. The chemical state of molybdenum (VI) in basic solution was studied by an anion-exchange technique. Evidence was obtained for the existence of polymeric species at pH-values up to 14. Preliminary work on the stability of Domax-1 anion exchange resin in perchlorate media indicates rapid deterioration even at 0.2F ClO4-.
- FLIP--AN IBM-704 CODE TO SOLVE THE PL AND DOUBLE-PL EQUATIONS IN SLAB GEOMETRY
- A method of obtaining the few-group form of the P/sub L/ and double-P/ sub L/ equations is given for slab geometry. Anisotropic scattering is allowed within specified limitations. The difference equations and associated recursion relations are discussed; the features and restrictions of FLIP are explained; and a detailed discussion of the input and output is presented. Operating intructions are given, and a sample problem is included. (auth)
- UNCOLLIDED FLUX FROM FINITE CIRCULAR AND RECTANGULAR CYLINDERS
- Expressions are derived for the uncollided flux from finite cylindrical sources with circular and rectangular cross sections. The source density is assumed to be completely arbitrary in the rectangular case and arbitrary to within independence of the aximuth in the circular case. The circular cylinder is assumed surrounded by an arbitrary number of concentric cylindrical shields and by plane circular shields above (or below) its upper (or lower) face. The rectangular source is treated with plane laminar shields parallel to one of its faces and with coaxial cylindrical shields. For both kinds of source geometry the point of observation is taken exterior to the source but without further restriction. The final expressions for the fluxes are in the form of volume integrals; they have not been reduced. (auth)
- CALCULATION OF THERMAL NEUTRON FLUXES IN PRIMARY SHIELDS
- A method is presented for calculating thermal neutron fluxes in the primary shields of reactor systems which eliminates reliance on mock-up experimental data. A multigroup P/sub 1/ approach is ernployed with the spatial dependence of the neutron sttenuation adjusted through use of a point source attenuation kernel for a homogeneous hydrogenous medium. Comparison of calculation with experiment is presentad. (auth)
- Gamma Ray Spectrometry
- No Description Available.
- USE OF THE "ACTION INTEGRAL" IN EW STUDIES
- No Description Available.
- Comments on Equipment for a PRTR Water Quality Control Laboratory
- This document describes required laboratory space and lists major equipment items necessary for a routine water quality laboratory in the P. R. T. R. Building. During discussions with R. D. Widrig and V. L. Rooney about the analytical sample program for the Plutonium Recycle Test Reactor, the author was asked to summarize equipment and space needs for a water control laboratory to provide routine analytical coverage on some of the water systems. Based upon 1706-KE-KER experience, some operating personnel may be used to provide analytical coverage on those routine analyses that are needed on around-the-clock basis with a savings of both time and money.
- Research in Photosynthesis
- The determination of the specific radioactivities of the chlorophylls and carotenoids of algae after photosynthesis with C/sup 14/O/sub 2/ is a formidable task, due to the extreme lability of these compounds. The whole success of the method depends on adequate chromatographic separations of the pigments from the colorless contaminants which are closely associated with them, and yet the time involved for such separations is sufficient for marked decomposition of the pigments to occur. It is suggested that the techniques of column chromatography, followed by centrifugallyaccelerated paper chromatography of the spectroscopically pure pigments, may resolve this problem. In an investigation of the action of cyanide on photosynthesis, green algae have been treated with radioactive cyanide. A multitude of products have been found to be formed in very short exposure times. One of these was identified with a material formed when algae are given radioactive CO/sub 2/ and nonradioactive KCN. This material has been identified as the cyanide addition product of ribulose-1,5- diphosphate. Upon hydrolysis it gives a branched-chain sugar acid (or mixture of isomers) closely related to hamamelonic acid. Perhaps the most important aspect of this work is the demonstration of the chemlcal role of cyanide. (auth)
- NITRIDED STAINLESS STEELS FOR HIGH-TEMPERATURE WATER SERVICE
- No Description Available.