Physical and Mechanical Properties of Some Aluminum-Lithium Alloys (open access)

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.
Date: November 18, 1952
Creator: Chiswik, H. H.; Lehrer, W. M. & Rideout, S. P.
System: The UNT Digital Library
Physics Division Supplement to Quarterly Report June, July, and August, 1953 (open access)

Physics Division Supplement to Quarterly Report June, July, and August, 1953

This technical report describes experimental nuclear physics, mass spectroscopy, crystallography, experimental reactor physics, theoretical physics (general), reactor theory, electronic digital computers, and applied mathematics and computations (general).
Date: November 1953
Creator: Turner, Louis Alexander, 1898-
System: The UNT Digital Library
Spectroscopy of Uranyl Salts in the Solid State (open access)

Spectroscopy of Uranyl Salts in the Solid State

From Introduction: "The interpretation of the fluorescence and absorption spectrum of the uranyl ion, indicated in this introduction, is based on the spectroscopic work of Nichols, Howes and co-workers (1914-1919), Dieke and van Heel (1925), Moerman and Kraak (1939), and Freymann and co-workers (1946-1948); on infrared studies (cf., Section 3 below) and Raman spectra; but most of all, on the work of Dieke, Duncan, and co-workers, carried out in 1943-1944 under the Manhattan District program. In the present chapter we will review briefly the earlier investigations in the field of uranyl salt and spectroscopy and give a somewhat more detailed summary of the results of Nichols and Howes and, particularly, of Dieke and co-workers."
Date: November 1953
Creator: Rabinowitch, Eugene
System: The UNT Digital Library
Dimensional Stability of Uranium Powder Compacts Upon Thermal Cycling (open access)

Dimensional Stability of Uranium Powder Compacts Upon Thermal Cycling

Thermal cycling tests on uranium have shown that the dimensional changes that occur on cycling in the alpha range are directly related to both the texture of the material and its grain size: cold rolled rods generally elongate in the direction of rolling, while the same rods, after a beta-treatment, grow at rates several orders of magnitude lower. This considerable improvement by beta-treatment has been attributed to the texture randomization accompanying the heat-treatment. In the course of this heat-treatment, however, considerable grain growth occurs, which ahs the effect of causing surface roughening on cycling (also referred to as "bumping"); fine grained material generally retains a smooth surface. These observations led to the speculation that the most desirable structure in uranium, from standpoint of dimensional stability, is one that combines both a random texture and a fine grain size. Heat treatment of rolled rod offered no easy method to obtain such a product; powder metallurgical techniques, however, appeared ideally suited for the purpose. To this end, early in 1949, the Sylvania Electric Products Company initiated a program to develop suitable techniques for producing uranium powder compacts having the above-mentioned desired characteristics. Because of the availability of thermal cycling equipment at Argonne, …
Date: November 30, 1953
Creator: Mayfield, R. M.; Zegler, S. T. & Chiswik, H. H.
System: The UNT Digital Library
Soluble Poisons in Reactor Control (open access)

Soluble Poisons in Reactor Control

Theoretical and experimental investigations of the use of soluble poisons (neutron absorbers) to supplement mechanical control rods are summarized. Experimental evaluation of poisons of interest includes in-pile and out-of-pile tests simulating anticipated reactor operating conditions. Other phases of the investigation included methods of poison injection, removal, and cleanup of poison-diluted reactor systems, as well as studies to evaluate possible application of soluble poison control in existing and proposed reactors.
Date: November 1955
Creator: Breden, Calvin Rudolph, 1901-; Brown, W. S. & Sivetz, M.
System: The UNT Digital Library
A Coated Cast Iron Crucible for use with Eutectic Al-Si Alloy in the Temperature Range 595°-650°C (open access)

A Coated Cast Iron Crucible for use with Eutectic Al-Si Alloy in the Temperature Range 595°-650°C

The feasibility of the coated metal crucible as a container for eutectic Al-Si alloy has been proven by test. Small, enamel-coated cast iron pots has been proven by test. Small, enamel-coated cast iron pots have successfully withstood the chemically aggressive Al-Si alloy and the adverse influence of an oxidizing atmosphere for a period of 3 months at 725°C. A similarly coated castiron crucible containing 450 pounds of eutectic Al-Si alloy was successfully tested for 144 days in a jacketing operation conducted at 595°-650°C. Under the same conditions, the normal service life of clay-bonded graphite and silicon carbide crucibles rarely exceeds 45 days. The coating material is a commercially available enamel capable of withstanding temperatures up to 790°C (1450°F). It is readily applied to the surface of a variety of ferrous metals and alloys; however, best results are obtained with alloys low in chromium and nickel which also have a low thermal expansion coefficient.
Date: November 1957
Creator: Yaggee, F. L.
System: The UNT Digital Library
Hazard Summary Report on the Argonne Low Power Reactor (ALPR) (open access)

Hazard Summary Report on the Argonne Low Power Reactor (ALPR)

Report regarding a nuclear reactor designed to operate in arctic conditions. This report includes a design of such a reactor and potential hazards.
Date: November 1958
Creator: Argonne National Laboratory. Reactor Engineering Division.
System: The UNT Digital Library
Advanced Designs of Magnetic Jack-Type Control Rod Drive (open access)

Advanced Designs of Magnetic Jack-Type Control Rod Drive

Report containing information regarding magnetic jacks, which are devices used "for positioning the control rods in a nuclear reactor, especially in a reactor containing water under pressure" (page 9). Contains a description of the device, its use, test results, and illustrations.
Date: November 1959
Creator: Young, Joseph N.
System: The UNT Digital Library
Gas-Cooled Reactors in the USA: A Survey and Recommendation (open access)

Gas-Cooled Reactors in the USA: A Survey and Recommendation

Report that provides "an understanding of the status of gas-cooled reactors as used for unclassified applications" and determining "phases of advanced research and development needed in the field and from these to recommend a program for high-temperature, gas-cooled reactors" (p. 5).
Date: November 1960
Creator: Armstrong, R. H.
System: The UNT Digital Library
A Process for the Recovery of Uranium From Nuclear Fuel Elements Using Fluid-Bed Drying and Volatility Techniques (open access)

A Process for the Recovery of Uranium From Nuclear Fuel Elements Using Fluid-Bed Drying and Volatility Techniques

From Summary: "The work described in this report is the application of this process to the recovery of uranium from highly enriched, low uranium-zirconium alloy plate-type fuels."
Date: November 1961
Creator: Levitz, N.; Barghusen, J.; Carls, E. & Jonke, A. A.
System: The UNT Digital Library
Status Report on the Argonne Advanced Research Reactor (open access)

Status Report on the Argonne Advanced Research Reactor

From Introduction: "This is a status report on the interim design and development for an advanced research reactor (AARR) that will produce a maximum thermal neutron flux of 5 x 10 to the fifteenth power neutrons/ (cm2) (sec). As a result, this report also contains sections covering shielding, plant layout, fuel charging, maintenance, and auxiliary facilities."
Date: November 1961
Creator: Lennox, D. H.; Barts, E. W.; Batch, R. V.; Beyer, F. C.; Jorgensen, G. L.; Kelber, C. N. et al.
System: The UNT Digital Library
Proceedings of the AMU-ANL Summer Study Program (open access)

Proceedings of the AMU-ANL Summer Study Program

From Introduction: "In 1954, the AEC presented the "five-year plan" for power reactor development, briefly outlined in Table I-1. The program proceeded and other reactors were added as a result of the incentives indicated in the outline."
Date: November 1962
Creator: Pearson, C. V.
System: The UNT Digital Library
A Method of Calculating Transient Temperatures in a Multiregion, Axisymmetric, Cylindrical Configuration the Argus Program, 1089/Re248, Written in Fortran II (open access)

A Method of Calculating Transient Temperatures in a Multiregion, Axisymmetric, Cylindrical Configuration the Argus Program, 1089/Re248, Written in Fortran II

From Abstract: "A detailed description is given of ARGUS, a FORTRAN II computer program for calculating transient temperatures in any concentric cylindrical configuration. Included are an explanation of the mathematical methods, a discussion of special features and restrictions, input and output descriptions, operating instructions, several sample problems, and the code listing."
Date: November 1963
Creator: Schoeberle, D. F.; Heestand, J.; Miller, L. B. & Miller, L. B.
System: The UNT Digital Library
Class Notes for a PL/I Course (open access)

Class Notes for a PL/I Course

Presented here are notes for a course in PL/I. They might serve as a guide to those who are developing a course, or as class notes for that course. They might be useful as a textbook independent of any course; as such a textbook, however, they are not self-contained because of the built-in assumption that they will supplement lectures and be accompanied by manuals. Very nearly the full language is taught here, with the emphasis on concepts rather than practical details. Discussion of I/O is avoided until roughly the midpoint of the course. The hoped-for consequence for students is an enhanced perception and understanding of the many concepts and their logical relationships. The dawning of the age of transportability for PL/I programs gives the user a reason, for the first time, to avoid convenient but illegal language.
Date: November 1975
Creator: Dritz, Kenneth W.
System: The UNT Digital Library
U-Pu-Zr Metal Alloy: a Potential Fuel for LMFBR's (open access)

U-Pu-Zr Metal Alloy: a Potential Fuel for LMFBR's

This report critically reviews the available information pertinent to the potential use of uranium-plutonium-zirconium alloy fuels clad with stainless steel in LMFBR's. The areas considered include breeding potential, burnup potential, thermal performance, fuel fabricability, fuel reprocessing, and safety considerations. Because information on uranium-plutonium-zirconium alloys is limited, wide use is made of experience with EBR-II metallic driver fuel to infer advantages and limitations of uranium-plutonium-zirconium fuels. It is concluded that sufficient potential exists for the applicability of uranium-plutonium-zirconium fuels to LMBFR's to warrant additional analytical and experimental studies.
Date: November 1975
Creator: Walter, C. M.; Golden, G. H. & Olson, N. J.
System: The UNT Digital Library
Benchmark Testing of the Finite-Strain Version of the LIFE-III Fast-Reactor-Element Code (open access)

Benchmark Testing of the Finite-Strain Version of the LIFE-III Fast-Reactor-Element Code

A collection of benchmark problems is used to test the finite-strain formulation of the LIFE-III fast-reactor fuel-element code. Analytical solutions for thick-wall cylinders loaded by internal and external pressure, valid for arbitrarily large strains, are presented for a linear viscous material. Similar problems are formulated for a nonlinear material, and numerical solutions are obtained using the Runge-Kutta method for the integration of an ordinary differential equation. These solutions are then compared with the corresponding solutions obtained using the LIFE-III code. With a proper choice of the number of spatial regions and time steps, good agreement is obtained between the two sets of solutions. The results indicate that the structural-analysis portion of the revised LIFE-III is valid for large strains.
Date: November 1976
Creator: Shack, W. J.; Jankus, V. Z. & Billone, Michael C.
System: The UNT Digital Library
Laboratory Studies for Separation of Solids from Synthoil Gross Product : Parts 1 and 2 (open access)

Laboratory Studies for Separation of Solids from Synthoil Gross Product : Parts 1 and 2

PART 1. A variety of surfactants and agglomerating agents have been added to coal-liquefaction product (from the SYNTHOIL process) to determine the effectiveness of these agents in decreasing the viscosity of the product or inducing agglomeration of suspended solids in the product (and consequently facilitating the removal of solids from the product). More than two dozen additives were tested; however, only two of the additives caused a small reduction in the viscosity of the coal-liquefaction product. PART 2. A variety of organic solvents have been added to coal-liquefaction product (from the SYNTHOIL process) to determine the effectiveness in promoting the precipitation of suspended solids in the product. High-temperature settling of the product in the absence of foreign solvent does not appear to be a promising mechanism for solids removal from this product. However, the promoter-solvent de-ashing scheme has been demonstrated to be a potentially attractive solids-liquid separation method, and kerosene has been found to be an effective promoter solvent for the SYNTHOIL gross product.
Date: November 1976
Creator: Huang, H. & Fischer, J.
System: The UNT Digital Library
PTA-1: A Computer Program for Analysis of Pressure Transients in Hydraulic Networks, Including the Effect of Pipe Plasticity (open access)

PTA-1: A Computer Program for Analysis of Pressure Transients in Hydraulic Networks, Including the Effect of Pipe Plasticity

The computer program PTA-1 performs pressure-transient analysis of large piping networks using the one-dimensional method of characteristics applied to a fluid-hammer formulation. The effect of elastic-plastic deformation of piping on pulse propagation is included in the computation. The program is particularly oriented toward the analysis of the effects of a sodium/water reaction on the intermediate heat-transport system of a liquid-metal-cooled fast breeder reactor, but may be applied just as usefully to other pulse sources and other piping systems. PTA-1 is capable of treating complex piping networks and includes a variety of junction types. Pipe friction and nonlinear velocity terms are included in the formulation. The program requires a minimum of input-data preparation and is designed to be easily used and modified. This report contains the governing equations, program structure, input requirements, program listing, and other information for PTA-1.
Date: November 1976
Creator: Youngdahl, C. K. & Kot, C. A.
System: The UNT Digital Library
Advanced Fuel Cell Development Progress Report: July-September 1977 (open access)

Advanced Fuel Cell Development Progress Report: July-September 1977

Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL).
Date: November 1977
Creator: Ackerman, J. P.; Pierce, R. D.; Nelson, P. A.; Arons, R. M.; Kinoshita, K.; Sim, J. W. et al.
System: The UNT Digital Library
Application of the Pulsed-Neutron Activation Technique for Flow Measurements at EBR-II (open access)

Application of the Pulsed-Neutron Activation Technique for Flow Measurements at EBR-II

This report describes the pulsed-neutron-activation (PNA) flow-measuring technique as applied to in situ fluid-flow measurement at EBR-II. Analytic relationships are derived for modeling the process and estimating the uncertainty in measurement. Results from measurements of both water flow and secondary-sodium flow are presented. Results from PNA measurements of water side of the EBR-II steam system have led better definition of plant parameters. Results from sodium-flow measurements are used to provide a correlation for in situ calibration of the electromagnetic sodium flowmeter in the secondary system.
Date: November 1977
Creator: Price, C. C.; Sackett, J. I.; Curran, R. N.; Livengood, C. L.; Kehler, P. & Forster, G. A.
System: The UNT Digital Library
Biaxial Creep Behavior of Ribbed GCFR Cladding at 650 degrees C in Nominally Pure Helium (99. 99%) (open access)

Biaxial Creep Behavior of Ribbed GCFR Cladding at 650 degrees C in Nominally Pure Helium (99. 99%)

Biaxial creep-rupture tests were conducted on 12 prototypic GCFR fuel-cladding specimens at 650 deg C and a nominal hoop stress of 241.3 MPa. All test specimens were fabricated from 20% cold-worked Type 316 stainless steel tubes that were ribbed on the outer surface by mechanical grinding or electro-chemical etching. Test variables included specimen length and the presence or absence of weld-reinforcing end collars.
Date: November 1977
Creator: Yaggee, F. L.; Purohit, A.; Grajek, W. J. & Poeppel, R. B.
System: The UNT Digital Library
Management of Waste Cladding Hulls (open access)

Management of Waste Cladding Hulls

This report reviews experience and research related to the pyrophoricity of zirconium and zirconium alloys. The results of recent investigations of the behavior of Zircaloy and some observations of industrial handling and treatment of Zircaloy tubing and scrap are also discussed. A model for the management of waste Zircaloy cladding hulls from light water reactor fuel reprocessing is offered, based on an evaluation of the reviewed information. It is concluded that waste Zircaloy cladding hulls do not constitute a pyrophoric hazard if, following the model flow sheet, finely divided metal is oxidized during the management procedure. Steps alternative to the model are described which yield zirconium in deactivated form and also accomplish varying degrees of transuranic decontamination. Information collected into appendixes is (1) a collation of zirconium pyrophoricity data from the literature, (2) calculated radioactivity contents in Zircaloy cladding hulls from spent LWR fuels, and (3) results of a laboratory study on volatilization of zirconium from Zircaloy using HCl or chlorine.
Date: November 1977
Creator: Kullen, B.; Levitz, N. M. & Steindler, M. J.
System: The UNT Digital Library
The Remote Working Level Monitor. Final Report (open access)

The Remote Working Level Monitor. Final Report

The Remote Working Level Monitor (RWLM) is an instrument used to remotely monitor the RN-daughter concentrations and the Working Level (WL). It is an ac powered, microprocessor based instrument which multiplexes two independent detector units to a single central processor unit (CPU). The CPU controls the actuation of the detector units and processes and outputs the data received from these remote detector units. The remote detector units are fully automated and require no manual operation once they are set up. They detect and separate the alpha emitters of RaA and RaC' as well as detecting the beta emitters of RaB and RaC. The resultant pulses from these detected radioisotopes are transmitted to the CPU for processing. The programmed microprocessor performs the mathematical manipulations necessary to output accurate Rn-daughter concentrations and the WL. A special subroutine within the program enables the RWLM to run and output a calibration procedure on command. The data resulting from this request can then be processed in a separate program on most computers capable of BASIC programming. The calibration program results in the derivation of coefficients and beta efficiencies which provides calibrated coefficients and beta efficiencies.
Date: November 18, 1977
Creator: Keefe, Donald J.; McDowell, William P. & Groer, Peter G.
System: The UNT Digital Library
DISPL: a Software Package for One and Two Spatially Dimensioned Kinetics-Diffusion Problems (open access)

DISPL: a Software Package for One and Two Spatially Dimensioned Kinetics-Diffusion Problems

DISPL is a software package for solving some second-order nonlinear systems of partial differential equations including parabolic, elliptic, hyperbolic, and some mixed types such as parabolic-elliptic equations. Fairly general nonlinear boundary conditions are allowed as well as interface conditions for problems in an inhomogeneous media. The spatial domain is one- or two-dimensional with Cartesian, cylindrical, or spherical (in one dimension only) geometry. The numerical method is based on the use of Galerkin's procedure combined with the use of B-splines in order to reduce the system of PDE's to a system of ODE's. The latter system is then solved with a sophisticated ODE software package. Software features include extensive dump/restart facilities, free format input, moderate printed output capability, dynamic storage allocation, and three graphics packages.
Date: November 1978
Creator: Leaf, G. K.; Minkoff, M.; Byrne, G. D.; Sorensen, D.; Bleakney, T. & Saltzman, J.
System: The UNT Digital Library