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  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: Atomic Energy Commission Reports
 Collection: Technical Report Archive and Image Library
6144-Channel Time-of-Flight Analyzer
Report describing a 6144-channel analyzer designed and built for the purpose of analyzing time-of-flight during studies of slow neutron scattering at Hanford Laboratories. This includes descriptions of the analyzer, its logic and circuits, and its test mode. digital.library.unt.edu/ark:/67531/metadc100653/
An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel
Report that "describes a nondestructive tester and some of its applications in measuring 10 to 100 µg of uranium surface contamination on unirradiated, low enrichment, uranium fuel elements" (p. ii). digital.library.unt.edu/ark:/67531/metadc100630/
Analog Computer Simulation of a Pulsed Extraction Column
Report describing "computer techniques used in the simulation and parameter determination, how the data were prepared for inclusion in the computer simulation, (and) methods used in presenting the results" (p. 3-4). digital.library.unt.edu/ark:/67531/metadc100655/
Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model
Report that describes Hanford Laboratories' overall N-Reactor plant simulation model and its use to study the characteristics of the plant, plant operational procedures, and the effects of plant, operator, and control system malfunctions. digital.library.unt.edu/ark:/67531/metadc100650/
Analysis of Meteorological Tower Data, April 1950 - March 1952, Brookhaven National Laboratory
Report issued by the Brookhaven National Laboratory discussing data collected from two BNL meteorological towers. As stated in the introduction, "results are presented in graphic form rather than tabular form" (p. 1). This report includes tables, maps, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc170954/
Analytical Chemistry Division Annual Progress Report: for Period Ending December 31, 1962
Report issued by the Oak Ridge National Laboratory discussing progress and work conducted by the Analytical Chemistry Division. Instrumentation, analytical methods, reactor projects, service analysis, and special research is presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc100408/
Analytical Chemistry Division Annual Progress Report for Period Ending November 15, 1964
Report issued by the Oak Ridge National Laboratory discussing progress and work conducted by the Analytical Chemistry Division. Instrumentation, analytical methods, reactor projects, service analysis, and special research is presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc100290/
Annual Report for 1963: Metallurgy Division
Report issued by the Argonne National Laboratory discussing work conducted by the Metallurgy Division during 1963. Annual experiments, programs, and studies are presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc170918/
Appendix to Preliminary Design 30,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission Idaho Operations Office Contract No. AT(10-1)-925
Report containing outlines of operating procedures, costs, construction, safety analysis, studies, and design specifications of a 30,000 kilowatt prototype partially enriched uranium nuclear power plant. digital.library.unt.edu/ark:/67531/metadc67309/
Appendix to Preliminary Design 55,000 KW Prototype Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission, Idaho Operations Office
Report containing documentation of projects undertaken by the multiple branches of the Health and Safety Division of the Idaho Operations Office at the Nuclear Reactor Testing Station (NRTS). digital.library.unt.edu/ark:/67531/metadc67251/
Applied Health Physics Annual Report for 1963
Report issued by the Oak Ridge National Laboratory discussing work and progress made by the Health and Physics Division during 1963. Instrumentation, personnel monitoring, and laboratory monitoring is presented. This report includes maps, tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc100291/
Applied Nuclear Physics Division Annual Progress Report for Period Ending September 10, 1956
Report issued by the Oak Ridge National Laboratory discussing work completed by the Applied Nuclear Physics Division during 1956. Summaries of experiments conducted and project developments are presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc100292/
Aqueous Homogeneous Reactors for Producing Central-Station Power
Report issued by the Oak Ridge National Laboratory discussing aqueous homogeneous reactors used in central-station power. As stated in the introduction, "it contains an evaluation of the potentiality of producing power only, as exhibited by aqueous homogeneous systems" (p. 6). This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc100317/
Area Survey Manual
Report issued by the Brookhaven National Laboratory discussing the area survey manual covering the 15 service stations. Design and operations of the service stations are presented. This report includes tables, illustrations, photographs, and a map. digital.library.unt.edu/ark:/67531/metadc170946/
The Area Survey Manual of Brookhaven National Laboratory: Area Radiation Detection Instrumentation, Maintenance, and Results
Report issued by the Brookhaven National Laboratory discussing the instrumentation, operation, and maintenance of the established area radiation monitoring stations. This report includes maps, tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc170923/
Argonne High-Flux Research Reactor: AHFR Conceptual Design Study
Report issued by the Argonne National Laboratory discussing high-flux research reactor design studies. As stated in the summary, "this report presents a reactor design to meet the needs of the basic research program at Argonne National Laboratory. The program requires some irradiation in thermal flux...and some beam experiments..." (p. 5). This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc67190/
Army Gas-Cooled Reactor Systems Program: Semiannual Progress Report, 1 January Through 30 June 1961
Report regarding the ongoing research and development related to the Army Gas-Cooled Reactor Systems Program. Includes status and progress of the program's projects, experiments, and data evaluations. digital.library.unt.edu/ark:/67531/metadc67302/
Army Reactors Program Annual Progress Report: for Period Ending October 31, 1962
Report summarizing ongoing nuclear work performed by the ORNL for the United States Army. digital.library.unt.edu/ark:/67531/metadc100409/
An Automatic Monitor for As76 Concentrations in Reactor Cooling Water
Report that describes the development, design, and operation of a prototype instrument meant to monitor the As76 concentration in reactor cooling water streams. digital.library.unt.edu/ark:/67531/metadc100623/
Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements
Report regarding the study of the calculated costs of fabricating plutonium-enriched fuel elements for Hanford Laboratories' Plutonium Recycle Program. Topics include descriptions of the process, design study of plants that use U235 and plutonium enriched fuel, and estimates of costs. digital.library.unt.edu/ark:/67531/metadc100620/
Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C
Report discussing the "equilibrium uranium distribution between an aqueous nitric acid solution and a 30 per cent by volume solution of tributyl phosphate in a hydrocarbon diluent" (p. 2). This includes the necessary equations. digital.library.unt.edu/ark:/67531/metadc100596/
Capture - Positron Ratios for Allowed and First-Forbidden Transitions
Report issued by the Brookhaven National Laboratory discussing capture positron ratios. As stated on page 1, "the purpose of this report is to present aids for the simple determination of the relative probabilities of K-electron capture and positron emission for allowed and first-forbidden transitions" (p. 1). This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc170957/
Chemical Processing Instrumentation and Control Research Program
Report regarding the chemical processing instrumentation designs and problems at the Idaho Chemical Processing Plant. digital.library.unt.edu/ark:/67531/metadc67260/
Chemical Technology Division Annual Progress Report: for Period Ending June 30, 1962
Report issued by Oak Ridge National Laboratory that discusses progress and work performed by the Chemical Technology Division. digital.library.unt.edu/ark:/67531/metadc100411/
Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1963
Report issued by Oak Ridge National Laboratory that describes research and progress at the Chemical Technology Division. digital.library.unt.edu/ark:/67531/metadc100412/
Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1969
Report documenting the ongoing research and development of the Oak Ridge National Laboratory's Chemical Technology Division. digital.library.unt.edu/ark:/67531/metadc100472/
Chemistry Division Annual Progress Report: for Period Ending June 20, 1962
Report issued by the Oak Ridge National Laboratory discussing progress and work conducted by the Chemistry Division. digital.library.unt.edu/ark:/67531/metadc100410/
Cobalt-60 Bulk Grain Irradiator: Study Report
Report issued by the Brookhaven National Laboratory discussing bulk grain irradiators. As stated in the abstract, "this report presents the results of a study to conceive, evaluate, review and estimate costs for a number of suitable designs for a Cobalt-60 Bulk Grain Irradiator; select a preferred type; and establish required criteria for future detail design and construction of the selected concept" (p. ii). This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc170974/
Comparison of Optimum Natural Uranium Nuclear Power Plant and Optimum Enriched Uranium Nuclear Power Plant
Report that "compares the designs of an optimum natural uranium power plant and an optimum partially enriched uranium power plant, both using CO2 as a coolant" (p. 1). Includes a description of each plant's design, construction, and economic considerations. digital.library.unt.edu/ark:/67531/metadc67307/
Completion Report for Contracts AT(10-1)-1054, AT(10-1)-1122 : Drilling, Casing and Cementing Observation Wells at the National Reactor Testing Station, Idaho
Report that "summarizes the costs, experience and results of contracts AT(10-1)-1054 and AT(10-1)-1122 for drilling, casing and cementing observation wells at the National Reactor Testing Station, Idaho" (p. [11]). digital.library.unt.edu/ark:/67531/metadc67257/
Computer Programs Using Zonal Harmonics for Magnetic Properties of Current Systems with Special Reference to the IBM 7090
Report that "discusses the magnetic vector and scalar potentials, magnetic field components and their derivatives, and flux linkage for single current systems, and the mutual inductance, forces and torques between two such systems, whose axes are coplanar but not necessarily coincident" (p. 1). digital.library.unt.edu/ark:/67531/metadc100425/
Condensation of Metal Vapors: Mercury and the Kinetic Theory of Condensation
Report issued by the Argonne National Laboratory discussing condensation theories of metal vapors. As stated in the introduction, "the objectives of this research then are critical analysis of condensation theories and data for metal vapors and experimental evaluation of the resistance to condensation for a representative metal such as mercury" (p. 18). This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc67199/
Consolidated Nuclear Steam Generator for Merchant Ship Application: A Conceptual Design
Report concerning the economic feasibility of pressurized water reactors for use aboard merchant ships. This includes conceptual designs and work remaining for the future of a Pressurized Water Reactor. digital.library.unt.edu/ark:/67531/metadc101006/
Corrosion Studies in Simulated N-Reactor Secondary System Water Environment
Report containing the procedures and results of tests made to determine the corrosion resistance of materials in a simulation of Hanford Laboratories' N-Reactor secondary system water environment. digital.library.unt.edu/ark:/67531/metadc100627/
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. digital.library.unt.edu/ark:/67531/metadc67194/
Critical Path Scheduling of ETR and MTR Reactor Shutdowns
Report describing a method for planning shutdown projects and scheduling the manpower to shut down Materials Testing Reactors (MTR) and Engineering Test Reactors (ETR). digital.library.unt.edu/ark:/67531/metadc67291/
A Critical Review of the Literature on Pressure Drop in Noncircular Ducts and Annuli
Report issued by the Oak Ridge National Laboratory discussing a compilation of literature on pressure drop in noncircular ducts. The literature compiled is presented, and analyzed. This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc100315/
Description of Facilities and Mechanical Components: Medical Research Reactor (MRR)
Report issued by the Brookhaven National Laboratory discussing the Medical Research Reactor at the Medical Research Center. Design, tests, and operations of the reactor are presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc170960/
Description of the Thermal Hydraulics Laboratory at Hanford
Report describing the thermal hydraulics facilities at Hanford Laboratories as well as its operation, equipment, and systems. digital.library.unt.edu/ark:/67531/metadc100589/
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. digital.library.unt.edu/ark:/67531/metadc67203/
Design Bases for ICPP Waste Calcination Facility
Report regarding a waste calcination unit that "will convert the fission product-containing aluminum nitrate solutions" "to granular alumina and fission product oxides" (p. 5). digital.library.unt.edu/ark:/67531/metadc67261/
The Design, Installation, and Testing of the Gas-Cooled Reactor UO₂ Irradiation Experiment at the NRTS
Report regarding sixteen experiments performed with a miniature re-entrant gas loop. Includes design problems and difficulties encountered, as well as their solutions. digital.library.unt.edu/ark:/67531/metadc67287/
Design of a Pilot Plant Facility for Radioactive Demonstration of the Pot Calcination Process
Report regarding the process development work at the Oak Ridge National Laboratory, including project objectives, design considerations, descriptions of equipment, and estimated costs. digital.library.unt.edu/ark:/67531/metadc67266/
Determination of Burnout Limits of Polyphenyl Coolants : Summary Report
Report documenting an investigation undertaken "to establish the burnout limits of a polyphenyl mixture (...), diphenyl, Santowax R, and monoisopropyl-biphanyl for various pressures, fluid velocities, and fluid temperatures" (p. 7). digital.library.unt.edu/ark:/67531/metadc67317/
Development and Demonstration of an Ion-Exchange Process for Kilogram-Scale Production of High Purity Promethium
Report regarding "the development of a process suitable for large-scale separation of highly purified promethium from the trivalent fission product rare earth mixture" (p. 3). digital.library.unt.edu/ark:/67531/metadc100632/
A Device for Recording Fuel Element Dimension on Punched Paper Tape
Report that "describes a system for translating the position of a strip-chart recorder potentiometer shaft into decimal digital form" (p. ii). digital.library.unt.edu/ark:/67531/metadc100624/
Dissolution of Power Reactor Fuel Cores
Report discussing the dissolution of simulated fuel cores. Equipment and procedures are discussed along with significant characteristics of the core materials. digital.library.unt.edu/ark:/67531/metadc100595/
Distribution of Uranium at Low Acid : Low Uranium Concentrations into 4-1/2 Percent TBP-AMSCO
Report wherein acid free uranyl nitrate hexahydrate was distributed into 4-1/2 percent TBP-Amsco 125-90W and combined with various concentrations of acid in order to study the distribution of uranium and hydrolysis effects. digital.library.unt.edu/ark:/67531/metadc67258/
Economic Evaluation of a 300 Mwe Fast Supercritical Pressure Power Reactor
Report regarding Hanford Laboratories' 300 Mwe fast supercritical pressure power reactor. This includes descriptions of the plant and reactor, their operations, safety systems, and plant economics. Appendices begin on page 107. digital.library.unt.edu/ark:/67531/metadc100635/
The Effect of Deionized Water on the Reactor Effluent Activities: Part 2 - Zirconium and Aluminum Clad Fuel
Report containing experimental data testing the hypothesis that aluminum reactor tubes were "the site of most radioisotope production in the deionized water cooled system" and that zirconium tubes provided "only nominal participation" (p. 2). digital.library.unt.edu/ark:/67531/metadc100645/
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