Technical Report Archive & Image Library (TRAIL) - 167 Matching Results
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- Calculations on U235 Fission Product Decay Chains
- Report of equations for calculating decay of U235. The introduction states" Calculations have been made on the U235 fission product decay schemes. The results for a typical example, that of a reactor operating at 1000 kilowatts for 180 days, have been tabulated and graphed. General formulae have been used so that the results can be applied for any power level and any time of irradiation" (p. 2).
- Aqueous Corrosion of Uranium and Alloys: Survey of Project Literature
- This report describes corrosion rate of uranium in hydrogen-saturated water appears to be constant with respect to time after a brief induction period and to involve only one type of over-all reaction, in which pitting effects are slight or nonexistent.
- Reactor Engineering Division Semiannual Report December 1, 1951 through May 31, 1952
- This report describes the construction of a reactor and the research conducted in the reactor such as solid fuel and liquid fuel research, boiling reactor experiments, CP-6 bond testing program, and water quality control experiments for CP-6 program.
- Chemistry Division, Section C-1, Summary Report for April, May, And June 1952
- Report describing the research and development activities related to nuclear chemistry and radiochemistry and basic chemistry conducted by the Argonne National Laboratory Chemistry Division, Section C-1.
- The Thermal Neutron Cross Section Of 9.2h Xe135 : Supplement to Report CP-2782
- In this report it reviews a possible declassification of the content of report CP-2782 (February 15, 1945) that presents the data of the most careful measurements of the thermal neutron cross section of 9.2h Xe135 and re-evaluation of the particular methods of measuring neutron flux employed in this experiment had been made for other purposes.
- A Capsule Design for Experimental High-Flux Irradiations Of Fuel Materials
- New reactors presently in design or construction stages, as well as revised operating procedures for existing reactors, have shown an increasing emphasis on extending the exposure time of the reactor fuel elements. However, operating experience at Hanford, as at other installations, has demonstrated that as the amount of burn-up in uranium metal is increased an increase is also noted in operational difficulties resulting from the dimensional behavior of the fuel. During reactor irradiation uranium slugs or rods have been observed to change in length and diameter, to warp, and to develop surface roughening.
- Physical and Mechanical Properties of Some Aluminum-Lithium Alloys
- The results of this study are tabulated in Summary Tables A and B below. For the most part, these values were read from smoothed curves drawn thru the plotted experimental data. The values for aluminum (i.e., 0 w/o Li) were taken from the 1948 Edition of the ASM Metals Handbook. The room temperature properties are reported for lithium contents of 0, 3.5, 7 and 10 weight per cent. In the case of the high temperature properties, there were insufficient data to allow extrapolation and interpolation to pre-chosen compositions: these properties are therefore reported only for the compositions of the actual samples.
- The Decomposition of Light and Heavy Water Boric Acid Solutions by CP-3' File Radiations
- The behavior of light and heavy water solutions of boric acid toward pile radiations has been investigated as a function of boric acid concertation. A study has also been made of the effect of hydrogen, hydrogen peroxide, and potassium iodide on the radiation stability of boric acid solutions.
- Reactor Engineering Division Quarterly Report September 1, 1952 through November 30, 1952
- Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
- Helium Leak Detector Test for Hanford And Savannah River Fuel Slugs
- The Helium Leak Detector Test provides a method for detecting the presence of minute holes, cracks, fissures, etc. in the aluminum jackets of Hanford and Savannah River reactor fuel slugs which would allow moisture to penetrate to the uranium during reactor operation.
- Metallurgy Division Quarterly Report [for] October, November, and December, 1952
- This quarterly progress report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses (1) water-cooled reactors, (2) liquid metal-cooled reactors, (3) reactor development - fuel metallurgy, (4) reactor development - component metallurgy, (5) basic metallurgy, (6) basic ceramics, (7) aqueous corrosion, and (8) applied metallurgy.
- Chemistry Division, Section C-II, Summary Report For April, May, And June 1952
- This report was written by different scientist on various experiments of solid state, physical chemistry, radiochemistry and analytical, and special problems.
- Chemistry Division, Section C-II, Summary Report for July, August, and September 1952
- This report deals with the (1.1) physical properties of graphite, (1.2) effects of pile irradiation on the properties of graphite, (1.3) effect of irradiation on "ceramic" materials, (1.4) effects of radiation on ice -- the x-ray induced luminescence of ice, (1.5) investigation of color centers and other optical properties of single crystals. (2.1) radiation chemistry of liquids, (2.2) application of mass spectrometry to chemical problems, (2.3) vapor pressure and heat of vaporization of uranium, (3.1) nuclear properties of Zr93 and Nb93m from fission, (3.2) mass distribution in the spontaneous fission of Cm242, (3.3) Upper limit to the lifetimes of the first excited states of Th236, U234, and Pu236, (3.4) on the one-body model of alpha radioactivity, (4.1) spectrographic analysis, (4.2) chemical analysis, (5.1) paramagnetic resonance measurements, and (5.2) the 60-inch cyclotron.
- Chemistry Division, Section C-II, Summary Report for July, August, and September 1952
- This report deals with the (1.1) physical properties of graphite, (1.2) effects of pile irradiation on the properties of graphite, (1.3) effect of irradiation on "ceramic" materials, (1.4) effects of radiation on ice -- the x-ray induced luminescence of ice, (1.5) investigation of color centers and other optical properties of single crystals. (2.1) radiation chemistry of liquids, (2.2) application of mass spectrometry to chemical problems, (2.3) vapor pressure and heat of vaporization of uranium, (3.1) nuclear properties of Zr93 and Nb93m from fission, (3.2) mass distribution in the spontaneous fission of Cm242, (3.3) Upper limit to the lifetimes of the first excited states of Th236, U234, and Pu236, (3.4) on the one-body model of alpha radioactivity, (4.1) spectrographic analysis, (4.2) chemical analysis, (5.1) paramagnetic resonance measurements, and (5.2) the 60-inch cyclotron.
- Technical Review of ZPR-1 Accidental Transient - the Power Excursion, Exposures, and Clinical Data
- On June 2, 1952, 15:52 hours, a large reactivity change was made manually in a ZPR-1 assembly causing a power excursion of about one kwh, which resulted in damage to the reactor core components and radiation exposure of some of the operating personnel to perhaps several rep. None of the contributing causes is reviewed here nor are the measures which were taken to reduce the probability of a recurrence discussed since these are considered administrative matters beyond the scope of this technical report. It is intended only to describe the incident, estimate the exposures and present available clinical data.
- Autoclave Testing of Mechanically Jacketed Thorium Slugs In Water
- Water corrosion tests on mechanically jacketed and pinholed thorium slugs show that these slugs fail in a manner similar to that observed for mechanically jacketed and tested uranium slugs. The proposed mechanism for the water corrosion of these jacketed slugs is analogous to the water corrosion mechanism of jacketed uranium slugs presented in the project lecture. A bare thorium slug appeared to be more resistant to corrosion by water than a mechanically jacketed slug during the first half of the autoclave test. After approximately 90 hours of testing both the bare and the mechanically jacketed thorium slugs were severely corroded by water.
- Summary of Meteorological Data Taken at Argonne National Laboratory, Du Page County, Illinois, July 1951 Through June 1952
- The report is the third in a series of interim reports on the climatological studies which are being conducted at the Argonne National Laboratory. First report appeared as document ANL-4538 and covered the period July, 1949 through June, 1950; the second report, ANL-4793, covered the period July, 1950 through June, 1951. These annual reports are offered for purposes of information only; broad conclusions regarding the climate of this site must await the accumulation of a statistically significant amount of data.
- Determination of Zirconium and Total Fluoride Ion in Zirconium - Hydrofluoric Acid Solutions
- An analytical method has been developed for zirconium and fluoride ions in the system resulting from the dissolution of fuel elements in hydrofluoric acid. The method is based on determination of the density and electrical conductivity of the dissolved metal solution.
- Progress Report on the Experimental Breeder Reactor April 1, 1951 Through January 31, 1953
- This report describes the progress on the experimental breeder reactor. It focuses on the approach to critical experiments, calibration of controls and flues and flux distributions.
- Physics Division Supplement to the Summary Report June Through November 1952
- This supplement includes reports on (1) transmission measurements with the fast chopper, (2) a search for Pu244, (3) crystallographic studies, (4) resonance flux in CP-[gamma], (5) multigroup methods for concentrated fast assemblies, (6) work on the ZPR-1 Reactor, and (7) work on the ZPR-II Reactor.
- Recovery of Uranium From Ore Concentrates
- The use of bromine trifluoride solution has been investigated for the preparation of purified uranium hexafluoride from ore concentrates. The best yields were obtained with the use of antimony pentafluoride solutions in bromine trifluoride, and less fluorine was consumed in the case of previously hydro fluorinated samples. This approach appears to be technologically sound and may prove economically superior to existing procedures in the case of newly constructed facilities.
- A Summary and Bibliography of Some Research on Radiation Damage in Ceramic Materials Performed at the Argonne National Laboratory
- The susceptibleness of certain "ceramic" substances to extreme radiation damage (such as that observed in graphite) as indicated by changes in dimensions and heat content is discussed in terms of the experimental evidence which is available.
- Reactor Engineering Division Quarterly Report : December 1, 1952 Through February 28, 1953
- Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, research, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
- Casting of Blanket Bricks, Ring, Plug, and Control Rods for the Experimental Breeder Reactor (CP-4)
- The cup assembly of the Experimental Breeder Reactor (EBR) consists of blanket bricks, inner rings, and safety plug, all of natural uranium. The design of the finish machined brick is shown in Figure 1. These pie shaped bricks when stacked together, 12 bricks arranged in circular form and stacked seven rings high, comprise the cylindrical portion of the outer blanket, 17.875" I.D. x 30.875" O.D. after machining and canning. The inner ring, which is shown in Figure 2, fits inside the bottom layer of bricks. The circular opening in the center of the inner ring is closed by the safety plug shown in Figure 3.
- Thermal Annealing of Neutron Induced Discomposition in Artificial Graphite : [Part] III, Heating-During-Irradiation Experiments
- Experiments are described in which the pile-induced changes in electrical resistivity and elastic modulus of graphite were investigated as functions of the sample temperature during bombardment and the amount of bombardment. The data are for relatively low bombardment times (up to ca. 20 L-units) and temperatures (up to 340*C) and are not sufficiently extensive to permit unequivocal conclusions.
- Effects of Metal Purity and Heat Treatment on the Corrosion of Uranium in Boiling Water
- Corrosion rates of present reactor grade uranium were measured in boiling distilled water and were found to have higher values almost by a factor of two then previously reported corrosion rates of uranium. Mallinckrodt biscuit metal showed corrosion rates in the same medium somewhat lower than reactor grade uranium, and high purity metal prepared at Argonne National Laboratory corroded considerably less rapidly than the biscuit metal.
- The Manufacture Of Enriched Uranium Fuel Slugs for the Experimental Breeder Reactor
- This report describes the specifications, materials and the sequence of operations used to found and fabricate the first charge of enriched uranium fuel in the Experimental Breeder Reactor.
- Development of a Process to Produce Zirconium Hanford Type Process Tubing by Roll Forming And Inert Arc Welding
- The development of methods which were successful in producing zirconium Hanford type process tubing by roll forming and inert are welding (He) flat strip to which appropriate rails had ben previously attached by resistance welding is described in this report. Grade 2 drip arc melted crystal bar material was used.
- Electronic Distribution Functions and Thermodynamic Properties at High Temperatures
- Report issued by the Argonne National Laboratory discussing the thermodynamics and electronic distribution of high temperatures. As stated in the introduction, "in the present paper, a model for computing is described which takes into account in detail the interactions between bound electrons and the average interaction of the bound electrons with the free ones" (p. 4). This report includes tables, and illustrations.
- The Isolation and Purification of Neptunium-237 Obtained From Hanford Wastes
- Through the efforts of the Hanford Engineer Works a quantity of neptunium-237 was separated from uranium waste solutions by a modification of the standard plutonium precipitation process, This material, as concentrates, was shipped to Argonne for final isolation and purification of the neptunium.
- Chemical Engineering Division Summary Report : January, February, And March 1953
- Dissolution of the large number of samples obtained from the natural uranium blanket of the Experimental Breeder Reactor after approximately 485,000 kw.-hr. of operation has been completed, and analysis of these samples for uranium consumed and plutonium formed is well along. An attempt is being made to distinguish quantitatively between uranium-238 and uranium-235 fission in the blanket area by determining the ratio of ruthenium-106 to cesium-137 in the fission products.
- Refractive Indices of the Systems Uranium Hexafluoride-Bromine Trifluoride and Uranium Hexafluoride-Bromine Pentafluoride
- A spectrometer has been used with a hollow prism electrically heated to 70 C to measure the refractive indices of solutions of uranium hexafluoride in bromine trifluoride and uranium hexafluoride in bromine pentafluoride. The refractive indices of the two binary systems have been expressed as a function of composition.
- Feasibility Report on Fast Exponential Experiment
- The general program established at Argonne National Laboratory in connection with the Fast Power Breeder Reactor (PBR) includes performance of exponential experiments on assemblies having compositions which may exist in the reactor core. This report deals with that phase of the program known as the Fast Exponential Experiment which may be described very briefly as follows. An assembly of fissile (U-235) and fertile material (too small to be self-critical) intermixed with poisons (such as are encountered in the mechanical structure and coolant system of a self-sustaining reactor) is fed with neutrons from an auxiliary source. By measurements of the neutron flux within the assembly, important parameters can be calculated which are necessary to the proport design of an actual critical reactor of the same composition.
- Plaster of Paris Replicas of Reactor Fuel Slugs
- A method is described for preparing plaster of Paris replicas of irradiated fuel slugs. An impression mold is made by pouring the plaster about a fuel slug held in a specially designed holder. The slug is removed from the holder and the impression mold issued to cast a replica, also made of plaster of Paris. The replicas, including one end only, are accurate reproduction of the original slug for surface features down to about one-half mil and for dimensions within one or two mills. Two dental impression plasters were found to give satisfactory results. With the limits mentioned, the process will serve the purpose of preserving models of radioactive specimens for use as "museum pieces." However, the procedures are very exacting in achieving such results.
- Reactor Engineering Division Quarterly Report March 1, 1953 through May 31, 1953
- Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
- Preliminary Report on Low Columbium: Uranium Corrosion Resistant Alloys
- Uranium alloys containing 3 and 6 w/o niobium have been prepared in which the impurity content is rather low. These alloys show very promising resistance to corrosion by water at 260 and 300 degree C. The corrosion resistance is exhibited in degassed water and in water which is saturated with air or oxygen at room temperature before testing.
- Deposition of Corrosion Products by Cataphoresis
- This report is a record of experimentation conducted intermittently over a period of two years and directed toward preventing deposition of transport corrosion products on fuel elements and other critical components in high-temperature, circulating water nuclear reactor. It includes the postulated mechanism for deposition, a description of experimental equipment, experimental data, results obtained from the experiments, and recommendations for future study.
- Corrosion of Plutonium Alloys in NaK
- A plutonium-aluminum alloy containing 4 atom per cent aluminum showed no attack after exposure to purified NaK for one month at 400 C in the absence of any oxide. The same specimen and other plutonium alloys, including pure plutonium, showed marked deterioration in shorter exposure in the presence of oxide films from a welded stainless steel container. Pure uranium was resistant even in the presence of such oxides.
- Dissolution of Uranium Oxide Arising From Slug Failure
- The purpose of this work was to study reagents which might be effective in dissolving uranium oxide produced during slug failures in water-cooled reactor systems. An aspect of this problem which has subsequently become of primary importance is the solubility or transportability of the oxide in pure water.
- The Use of the Electrical Conductivity of Graphite as a Radiation Damage and Flux Monitor. Implications of the Results to the General Theory of Radiation Damage
- A method for monitoring radiation damage irradiations using the change of the electrical conductivity of graphite is described. Results of monitoring operations in a number of locations are given. An attempt is made to explain the damage rate found in the converter at CP-3. An estimate of the flux spectrum in VT-4 and the converter of CP-3 is made and the damage rate is computed according to theories of Seitz and James. It is found that the experimental results are more in accord with the predictions of Seitz. A number of corrections to James' report, ORNL-307, are noted in an appendix. It is shown that some information about the fast flux spectrum can be inferred from the radiation damage rate.
- Critical Studies with G. E. Type Fuel Elements
- The ZPR-I is a facility to study low power critical assemblies using enriched uranium as fuel, having a light water moderator and an essentially infinite water reflector on all sides. The fuel is held in elements 43" long with a 1" square cross section. Any of these elements may be placed in or removed from any position in the reactor tank. Thus, any desired core configuration may be easily obtained.
- The Electrolytic Refining of Uranium
- This technical report describes work done on the electrolytic refining of natural uranium in fused salt baths composed of various eutectics of alkali metal chlorides in which were dissolved UF, or UCl3.
- Engineering Properties of Diphenyl
- Report issued by the Argonne National Laboratory discussing engineering properties of diphenyl. As stated in the abstract, "data collected from the literature on the vapor pressure, enthalpy, liquid density, and vapor density of pure diphenyl are presented. A Mollier diagram, a temperature entropy diagram, and data on viscosity of diphenyl as a function of temperature are also presented" (p. 5). This report includes tables, and illustrations.
- An Improved Continuous Ether Extractor for the Determination of Uranium in Dissolver Solutions
- An improved continuous ether extractor is described. The modifications include a means of safely disposing of the active raffinate and a means of positivity checking the raffinate for completeness of uranium extraction. The results obtained on synthetic samples and on dissolver solutions are given. This work was undertaken because of a need for the determination of uranium in dissolver solutions with an accuracy of 0.1 per cent. After a review of available methods it was decided that a gravimetric determination would meet the requirements of precision and accuracy.
- Corrosion and Stability Tests on Chemical Poisons in Higher-Temperature Water
- Corrosion-stability tests have been made in static autoclaves at 500 and 600F on solutions of compounds having high neutron cross sections to evaluate their usefulness for shutdown purposes. The only compound tested which appeared to be completely stable in 600F water was boric acid. Limited corrosion data did not show it to cause excessive corrosion of zirconium or stainless steel.
- Preferred Orientation in 300 C Rolled and in Recrystallized Uranium Sheet
- The rolling and recrystallization textures in 300 C rolled uranium sheet were investigated using a Geiger counter diffractometer with the modified Schulz reflection technique. Seven sections of sheet material were used in order to obtain sufficient data for quantitative pole figures by the reflection technique. A special integrating specimen table was used for obtaining and recording the data atomically.
- Reactor Engineering Division Quarterly Report June 1, 1953 through August 31, 1953
- Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs (including the Power Breeder Reactor (PBR) and the Central Station Water Reactor (CSWR)), designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
- Comparative Analysis of ANL High Purity Uranium
- In the course of the development at Argonne of high purity uranium metal in ingot form, some questions arose as to the validity of the chemical analyses of some of the impurities (particularly those for carbon, boron, and silicon), with one analytical laboratory reporting concentrations in some instances of an order of magnitude greater than another laboratory. Since the low concentrations of impurities in this material involved, in some cases, the development of modified analytical procedures and standards, it was decided to check these discrepancies by having identically prepared samples analyzed by several AEC and associated laboratories. This report is a compilation of the results obtained.
- The Development of Equipment and Methods for Centrifugally Casting Reactor Fuel Slugs
- This technical report describes the design and construction of equipment and the development of methods for multiple mold, centrifugal casting of reactor fuel slugs. Advantages of the centrifugal casting method over the conventional fabrication methods were found to be (1) fewer operations, (2) fewer and more easily recovered residues, (3) less expensive equipment, and (4) the production of fuel slugs in shapes and in alloys not well adapted to other methods of manufacture. The method consisted of vacuum melting the alloy in stoppered crucibles and bottom pouring into a spinning rotor carrying 16 radially arranged copper molds. The castings so produced were used without further processing, except for cropping the sprue end to obtain the specified length.
- Metallurgy Division Quarterly Report July, August, and September 1953
- This quarterly report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses water cooled reactors, liquid metal cooled reactors, reactor development metallurgy, basic metallurgy, applied metallurgy, and aqueous corrosion,