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- Reactor Development Program Progress Report: April 1963
- Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during April 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
- Reactor Development Program Progress Report: March 1963
- Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during March 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
- Reactor Development Program Progress Report: May 1966
- Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during May 1966. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
- Reactor Development Program Progress Report: November 1965
- Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during November 1965. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
- Reactor Development Program Progress Report: September 1966
- Report issued by the Argonne National Laboratory discussing progress made within the Reactor Development Program for September, 1966. The report includes highlights of the different project activities including plutonium utilization, fast breeder reactors, general reactor technology, advanced systems research, and nuclear safety. This report includes tables, illustrations, and photographs.
- The Transient Behavior of Single-Phase Natural Circulation Water Loop Systems
- Report issued by the Argonne National Laboratory discussing single-phase water loop systems. As stated in the introduction, "the principal objective of this study was to determine the reliability of the calculations based upon numerical solutions of finite-difference energy and flow equations" (p. 9). This report includes tables, illustrations, and photographs.
- 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.
- Survey and Status Report on Application of Acoustic-Boiling-Detection Techniques to Liquid-Metal-Cooled Reactors
- Report issued by the Argonne National Laboratory discussing acoustic-boiling-detection techniques. As stated in the abstract, "this report summarizes literature through June 1967 concerning acoustic methods. In the acoustic method for boiling detection, either acoustic waveguides or high-temperature acoustic sensors are recommended" (p. 1). This report includes tables, and illustrations.
- Argonne National Laboratory Annual Report: 1956
- Report issued by the Argonne National Laboratory discussing the variety of work done at the laboratory during the year of 1956. This report includes tables, illustrations, and photographs.
- Argonne National Laboratory Annual Report: 1957
- Report issued by the Argonne National Laboratory discussing the variety of work done at the laboratory during the year of 1957. This report includes tables, illustrations, and photographs.
- Argonne National Laboratory Annual Report: 1958
- Report issued by the Argonne National Laboratory discussing the variety of work done at the laboratory during the year of 1958. This report includes tables, illustrations, and photographs.
- The EBWR: Experimental Boiling Water Reactor
- Report issued by the Argonne National Laboratory discussing the Experimental Boiling Water Reactor (EBWR) power plant. Designs of the final EBWR power plant are presented. This report includes tables, illustrations, and photographs.
- Midwest Tandem Cyclotron: A Proposal for a Regional Accelerator Facility
- Report issued by the Argonne National Laboratory discussing the proposal of the Midwest Tandem-Cyclotron accelerator facility. Descriptions of the facility designs, methods, and operations are presented. This report includes tables, illustrations, and photographs.
- Operating Manual for the Argonaut Reactor
- The design of the Argonaut (Argonne Nuclear Assembly for University Training) was initiated by the Reactor Engineering Division of Argonne National Laboratory to satisfy needs for a low-power reactor facility within the Laboratory, and for training uses within the international School of Nuclear Science and Engineering (ISNSE). It was intended primarily for instruction and research in reactor physics. It was also considered as a possibility that it would fulfill the requirements of universities engaged in a program of nuclear science. The cost of the facility was to be kept to a minimum consistent with the high degree of inherent safety and a great amount of flexibility in the system. The basic design stemmed from the Knolls Atomic Power Laboratory Thermal Test Reactor* (TTR), now called Nuclear Test Reactor (NTR). Modification during the course of the work justified the new name "Argonaut".
- Summary of Meteorological Data Taken at Argonne National Laboratory, Du Page County, Illinois, July 1952 Through June 1953
- Report issued by the Argonne National Laboratory discussing meteorological data collected between 1952 and 1953. Wind, temperature, pressure, and precipitation studies are presented. This report includes tables, illustrations, and a map.
- Annual Report 1961
- This seventh Annual Report is a summary of some of the progress in scientific and engineering research and development carried on at Argonne National Laboratory during 1961. As is customary in this series, only those portions of the total program that have reached such a stage that they may be of general interest are recorded. Thus, a comparison with the Annual Reports for 1959 (ANL-6125) and for 1960 (ANL-6275) will reveal the description of a generally different set of scientific activities. A more detailed presentation of any work covered in this report or of the many ANL projects not mentioned may be obtained by perusing the various progress and topical reports issued by the Laboratory during 1961. A list of the publications in the scientific journals during 1961 by Argonne personnel has been given as an Appendix.
- Argonne National Laboratory Idaho Division Summary Report: July-September, 1960
- Report issued by the Argonne National Laboratory covering a summary report of the work conducted by the Idaho Division. Experimental work and progress made on reactors are presented. This report includes tables, illustrations, and photographs.
- Argonne National Laboratory Idaho Division Summary Report: October 1960-March 1961
- Report issued by the Argonne National Laboratory discussing a summary of projects conducted with the Idaho Division. Descriptions of each project are presented. This report includes tables, and illustrations.
- Particle Accelerator Division Summary Report: April 15, 1958 through October, 1958
- Report issued by the Argonne National Laboratory discussing a summary report of work completed between April and October, 1958. Summaries of the studies conducted and work completed are presented. This report includes tables, and illustrations.
- 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.
- 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.
- Reactor Engineering Division Quarterly Report: December 1, 1953 Through March 30, 1954
- 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.
- Reactor Engineering Division Quarterly Report, June 1, 1949 - August 31, 1949
- 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.
- 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.
- 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.
- Reactor Engineering Division Quarterly Report September 1, 1953 through November 30, 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.
- 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.
- Engineering, Construction and Cost of the Argonaut Reactor
- Report describing the Argonaut Reactor located at the Argonne National Laboratory. Photographs and descriptive drawings of the reactor are included.
- Flow-Regime Transitions at Elevated Pressures in Vertical Two-Phase Flow
- Two-phase flow-regime transitions at elevated pressures for a single-component, trichloromonofluoromethane, were investigated for forced-circulation, upward flow in a vertical, rectangular conduit with internal dimensions of 0.380 by 1.050 inches.
- 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.
- 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.
- Roll Cladding of Uranium-Niobium Alloys for Plate Type Fuel Elements
- The feasibility of cladding plate type, corrosion resistant uranium-niobium fuel elements with Zircaloy-II by roll bonding has been demonstrated. Plates with cores of uranium alloyed with 3 w/o and 6 w/o Nb intended for irradiation testing in a high temperature water test loop in the MTR have been finished withing specified tolerances. The preparation of cladding billet core and clad components and the assembly of billets by enclosing cores in welded Zircaloy-II jackets can be readily accomplished with conventional fabrication equipment. Some machining operations and billet evacuations, as used in the preparation of most picture frame billet assemblies have been eliminated. Roll bonds were obtained with reductions of 75% to 80% in thickness. Reductions in excess of 90% in thickness, although not necessary for bonding , can be used for economical productions of long plates. Plates can be made with clad to core bond strengths from 30,000 psi to 60,000 psi. Properly heat treated plates have sufficient ductility to allow cold finishing by rolling, forming, bending, or twisting, with reductions of 20% to 30%. Edge bonds of Zircaloy to Zircaloy have been obtained which were corrosion resistant to 260 C water. End seals which were also corrosion resistant to water at this temperature have been made by shielded arc welding inserts to the clad.
- Progress Report on the Argonne-Oak Ridge Digital Computer
- Report issued by the Argonne National Laboratory discussing a progress report on the Argonne-Oak Ridge digital computer. This report is an interim report, whose primary value is that it has forced those engaged in the work to give concrete expression to what they have been doing and thinking about up to this point. 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.
- 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.
- 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.
- 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.
- 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.
- 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.
- Summary of Conference on the Toxicity of Carbon 14 Held at Argonne National Laboratory, January 15-16, 1952
- Report issued by the Argonne National Laboratory discussing the Conference on the Toxicity of Carbon 14. At the outset of the meeting it was emphasized that the group was brought together to discuss work which had a bearing on the toxicity of C14 compounds used either clinically or industrially, and the hope was expressed that the group might be able to reach some conclusions on these matters. This report includes tables.
- A Hybrid-Computer Program for Transient Temperature Calculations on TREAT Fast Reactor Safety Experiments
- Report issued by the Argonne National Laboratory discussing a computer program used for fast reactor safety experiments. As stated in the summary, "this report gives a detailed description of a hybrid-computer program for calculating temperatures in a multi-region, axisymmetric, cylindrical configuration consisting of solid materials bounded by flowing coolant. Included is an explanation of the mathematical methods, together with a discussion of special features, input-output descriptions, and several sample problems" (p. 7). This report includes tables, and illustrations.
- Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant
- Report issued by the Argonne national Laboratory discussing a technical and economic evaluation of a direct-cycle light-water boiling reactor designed for natural circulation and internal steam-water separation. The reference 100-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. This report includes tables, and illustrations.
- Design and Testing of a High-Heat Flux Electron-Bombardment Heater
- Report issued by the Argonne National Laboratory discussing the testing of an electron-bombardment heater. As stated in the abstract, "the applications of electron-bombardment heating to liquid-metal heat transfer and reactor safety experiments are discussed. The design of a high-heat-flux, electron-bombardment heater (EBH) is presented" (p. 7). This report includes tables, illustrations, and photographs.
- The Regeneration Factor as a Function of Time in a Th232 - U235 Thermal Reactor
- This technical report is concerned with a theoretical investigation of the variation of the regeneration factor [gamma] in a Th232 - U235 thermal reactor. The abundances of the significant isotopes in the thorium-uranium cycle have been derived as a function of irradiation time at constant reactor power. The change in [gamma] as a function of irradiation time at constant power was calculated for combinations of enrichment and resonance escape probability considered likely to exist in a thermal reactor. The effect upon [gamma] of the the absorption cross section of 91Pa233 and of the fission products has been shown.
- Reactivity as a Function of Irradiation Time in Thermal Reactors
- Equations governing the variation of U235. U238, Pu239, Pu240, and Pu241 have been derived and their solutions plotted as a function of irradiation time. The initial U235 content of the uranium was varied from 0.5% to 2.0%. The range of conversion ratios was from 0.5 to 1.2. The irradiation was from 0 to 20,000 mwd/ton of fuel. Since a range of initial conversion ratios is associated with each value of enrichment, a solution results in a family of curves for each isotope, and, since the range of enrichments is large, the number of curves is quite large. Translation of the isotope curves to reactivity variation necessitates a calculation requiring a modest amount of time for a particular case but a prohibitive amount of time to cover the entire range of possible combinations of enrichment and initial conversion ratios. Reactivity variation as a function of irradiation time has been computed for a natural uranium reactor with an initial conversion ratio ranging from 0.7 to 1.2 and for 3 types of reactors in which there is a considerable current interest. Similar calculations for other reactors can be made by making use of the isotope curves and the calculation technique set forth in this report.
- Effects of Preferred Orientation and Grain Size On Dimensional Stability of Uranium on Thermal Cycling and Irradiation : Final Report -- Metallurgy Program 5.1.7
- The growth of alpha-rolled uranium rods on thermal cycling has been shown to depend on both preferred orientation and grain size. Preferred orientation appears to be a necessary condition for growth to occur; the extent of the growth depends upon the sharpness and type of texture developed and on the grain size. The highest growth rates occur in specimens with highly developed textures coupled with small grain sizes. The growth rates increase with cycling level, particularly in specimens of large grain size.
- Growth Rates and Microstructural Characteristics of 300 C Rolled Uranium Rods on Thermal Cycling
- The thermal cycling growth and the accompanying metallographic changes were studied in 300 [degree] C rolled uranium rods up to 3000 cycles. The growth rate was found to decrease at the higher cycling levels. Project-grade material developed substantial porosity during cycling; high purity material showed no evidence of porosity.
- 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.
- Particle Accelerator Division Summary Report: April Through September 1960
- Report issued by the Argonne National Laboratory discussing a summary report of the Particle Accelerator Division. As stated in the summary, "this report outlines two methods applicable respectively to longhand and computer calculations" (p. 4). This report includes tables, illustrations, and photographs.
- A Physical Determination of the Conversion Ratio of the Experimental Breeder Reactor
- Report issued by the Argonne National Laboratory discussing the Experimental Breeder Reactor (EBR). Descriptions and methods of the EBR are presented. This report includes tables, and illustrations.