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- 200-Mwe Prototype Large SGR: Reactor Structure Design and Evaluation
- From abstract: This document presents the reactor structure design and evaluation for a 200-Mwe prototype large SGR.
- Addendum to the Spert IV Hazards Summary Report: Capsule Driver Core
- From abstract: "explain all important features pertaining to a new pulsed irradiation reactor, the Capsule Driver, Core, and to analyze the potential problems and hazards of operating this reactor in the existing Spert IV facility."
- 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.
- Annual Technical Progress Report, AEC Unclassified Programs: 1965
- Annual report describing progress on unclassified research programs funded by the U.S. Atomic Energy Commission during the 1964-65 fiscal year.
- Application of Nuclear Power Plants (SNAP Units) to the Manned Orbiting Research Laboratory (MORL)
- Abstract: This report describes in detail two designs of a nominal 6-kwe Nuclear Power Plant (NPP), one using thermoelectrics for power conversion and the other using the Mercury-Rankine cycle NPP.
- Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1964
- Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
- Calandria Core Weld Joint Development
- Abstract: The design and initial test of cutting and welding equipment developed to remotely cut and re-weld the bottom process tube joint are discussed in this report.
- Calculations of the Madelung Constant and Inverse Twelfth Power Repulsion Factors for the Wurtzite Crystal Structure
- From abstract: The Madelung constant and the inverse twelfth power repulsion factor have been calculated for the wurtzite structure for wide ranges of the crystal parameters and u.
- Carbide Fuels in Fast Reactors
- Abstract: Cladding and fuel material processing prospects are reviewed, and fuel system possibilities for near-term (~1 mill/kwh) and long-range (<0.5 mil/kmh) fuel cycles are described.
- Comparative Fuel Cycle Evaluations, Low Decontamination Pyroprocessing, and Aqueous Reprocessing: Part 2. UC Fuel in a Thermal Reactor
- From abstract: Preliminary cost estimates for fuel cycles using both aqueous and CARBOX reprocessing are presented.
- Corrosion of the Volatility Pilot Plant INOR-8 Hydrofluorinator and Nickel 201 Fluorinator During Forty Fuel-Pprocessing Runs with Zirconium-Uranium Alloy
- Report documenting the corrosion of fluorinators of the Oak Ridge National Laboratory's volatility pilot plant. Includes descriptions of the fluorinators, their operating environments, and the results of their corrosion.
- Development, Acceptance and Qualification Testing of the SNAP 10A Ejectable Heat Shield
- From abstract: The development, acceptance, and qualification tests performed on the SNAP-10A Ejectable Heat Shield and components, the results of those tests, and the conclusions drawn from the results are presented in this report.
- The Development of an Improved Thermionic Energy Converter: Third Quarterly Technical Report
- From introduction: The objective of the current program is to determine the feasibility of the reservoirless converter operation by conducting a series of tests on operating thermionic converters which contain cesium in the vapor phase only.
- Development of High-Temperature Electrical Ground Test Heaters for the SNAP 10A Program
- Introduction: The development and qualification of the system acceptance test heaters and the reactor simulator heater are described in this progress report.
- Effect of Carburization on the Low Strain Rate Behavior of Type 304 Stainless Steel: Interim Report
- Abstract: Pressure stress-rupture specimens of thin walled Type 304 stainless steel tubing have been tested at temperatures to 1300°F in the presence of an internal diffusion limited carbon source.
- Fast Flux Test Facility Studies Progress Report: April 1965
- From abstract: "...limited study work was performed on the conceptual design of the proposed fast flux test facility and information was obtained in important areas of supporting technology."
- Fatigue Characteristics of 37-Tube, Modular, Steam Generator Head
- Abstract: This report presents the pertinent results of a series of fatigue tests relating to the evaporator and superheater 37-tube module heads for the sodium heated steam generator described in NAA-SR-9826.
- Final Design of Sodium-Heated, Modular, Steam Generators for the SCTI
- Abstract: The following report covers the final design of the modular steam generators.
- Final Report: Investigation of Boiling Flow Regimes and Critical Heat Flux
- From abstract: A program to investigate the mechanism of the critical heat flux condition from the standpoint of flow regimes has been initiated at Dynatech for the AEC. This report covers the work done on this investigation in the first year.
- Flight Data and Results of Radiochemical Analyses of Filter Samples Collected During 1961 and 1962
- Report containing "flight data and (...) results of radiochemical analyses of stratospheric and tropospheric air filter samples collected during Project Star Dust. This report contains data for samples collected during June 1961 to December 1962, the first year and a half of the project" (p. 2).
- Flux Control for Irradiation Experiments
- Abstract: This report reviews various means which have been used to control experimental conditions in irradiation experiments, and presents the concept of local flux control.
- Gas-Cooled Reactor Project Semiannual Progress Report: September 1964
- Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Gas-Cooled Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
- Gas-Cooled Reactor Project Semiannual Progress Report: March 1965
- Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Gas-Cooled Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
- The HASL Bone Program 1961-1964
- Report documenting the measuring of strontium-90 levels contained in the bones of children and adults of various age brackets across the United States.
- The HASL Surface Air Sampling Program Summary Report For 1963
- Report that summarizes the first year of the Surface Air Sampling Program, including the results of analyzing 1,700 air filter samples and 400 precipitation samples.
- Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1964 - March 1, 1965
- Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
- Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1965 - June 1, 1965
- Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
- Health and Safety Laboratory Fallout Program Quarterly Summary Report: September 1, 1964 - December 1, 1964
- Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
- High-Density Concrete for Gamma and Neutron Attenuation
- Report issued by the Oak Ridge National Laboratory discussing the development of a high-density concrete. As stated in the abstract, "the basic approach to high-density concrete mix design is reviewed to show that theoretical calculations for concrete mixes do give results that are reliable" (p. 1). This report includes tables, illustrations, and photographs.
- The High-Temperature Irradiation Behavior of Hypostoichiometric Uranium Monocarbide
- From abstract: A series of three multi-compartmented experiments was designed to investigate the irradiation behavior uranium carbide fuels, as a function of composition, temperature, and burn-up; and the mechanical properties of Type 304 stainless steel, as a function of temperature and integrated thermal neutron flux.
- Increasing Thermocouple Reliability for in-Pile Experiments
- Abstract: The results indicated that increased reliability can be obtained by using thermocouples made with insulation of increased density and/or a low thermal expansion sheath.
- INDEX: a Computer Program for Indexing X-ray Diffraction Powder Patterns
- From introduction: "...a logical system has been developed to yield rapidly the indexing of a given powder pattern by using an electronic computer."
- Instrumentation and Control Practices in U.S.A. Reprocessing Plants
- Report surveying the "[i]nstrumentation and control practices at the Hanford Plant, the Idaho Chemical Processing Plant, the Oak Ridge national Laboratory, and the Savannah River Plant" (p. iv).
- Irradiation Swelling, Phase Reversion, and Intergranular Cracking of U-10 wt % Mo Fuel Alloy
- Abstract: A fuel development program has been conducted, to investigate the behavior of U-10 wt% Mo alloy at the fission rates and temperatures anticipated in Core I of the Hallam Nuclear Power Facility.
- Large SGR Control Rod Development
- From abstract: A development program was initiated to design, fabricate and test an absorber column with a 10 to 12 year lifetime, for use in the proposed LSGR.
- Liquid MHD Power Cycle Studies
- Report issued by the Argonne National Laboratory discussing the magnetohydrodynamics (MHD) power cycle for liquid metals. The benefits, and different phases of the MHD power cycle are presented. This report includes tables, and illustrations.
- Maritime Reactor Project Annual Progress Report for Period Ending November 30, 1963
- Report issued by the Oak Ridge National Laboratory discussing annual progress made by the Maritime Reactor Program. Progress and studies conducted during 1963 are presented. This report includes tables, illustrations, and photographs.
- Measurement of α, the Ratio of the Neutron Capture Cross Section to the Fission Cross Section, for ²³⁵U in the Energy Region from 3.25 eV to 1.8 keV
- Report issued by the Oak Ridge National Laboratory discussing techniques to obtain measurements of alpha for enriched uranium. Descriptions of equipment and experiments used to obtain alpha are presented. This report includes tables, and illustrations.
- Metallurgy Research Operation: Quarterly Progress Report, January - March 1965
- Quarterly progress report on a project to test the radiation effects on metallurgy.
- Microscopic and Autoradiographic Studies of Distribution of Uranium in the Rat Kidney
- Report issued by the Oak Ridge National Laboratory discussing studies conducted on uranium retention in rat kidneys. Methods, equipment, and results of the studies are presented. This report includes tables, illustrations, and photographs.
- MINIMIZER: A Computer Code for Determining Minimum Fuel Cost
- Report that describes the Hanford Laboratories MINIMIZER code and demonstrates its accuracy in providing fissile fuel costs in a precise and automatic manner.
- Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965
- Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Progress of operations, construction, engineering analysis, and development is presented. This report includes tables, illustrations, and photographs.
- The NAA 47 U - 10 Mo Fuel Irradiation Program for HNPF Core 1
- Abstract: Atomics International conducted a fuel irradiation program to investigate and define the behavior of U-10 Mo fuel at the temperatures and fission rates anticipated in Hallam Nuclear Power Facility (HNPF) Core I.
- Optical Mapping of Oak Ridge Research Reactor Experiment Tubes
- Report issued by the Oak Ridge National Laboratory discussing optical mapping of experiment tubes. Descriptions of experiment equipment, and designs of the tubes are presented. This report includes tables, illustrations, and photographs.
- Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 5: July-December 1964
- Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
- Post-Test Physical, Chemical and Metallurgical Analysis of SNAPTRAN-3 Fuel
- The fuel element damage which occurred during the SNAPTRAN-3 Destructive Test of a Snap 10A/2 reactor is described. Chemical analysis of the fuel indicated that approximately 15% of the hydrogen was released and that the core flux was higher toward the center both radially and axially. Metallurgical analysis of the fuel determined the presence of the epsilon, delta, and gamma phases in the grain structure and evidence of a possible alpha or beta phase.
- The Properties and Irradiation Behavior of U₃Si₂
- Abstract: A limited study of the compound U₃Si₂ has been made in reference to its use as a prospective nuclear fuel in sodium cooled reactors.
- Quarterly Progress Report, Research and Development Activities Fixation of Radioactive Residues: April-June 1965
- Introduction: "This progress report is the twenty-sixth in a series presenting research and development activities in the field of radioactive wastes. Experimental work charged to programs other than those of the Division of Reactor Development is included for general interest and completeness; such work is identified in the headings."
- Quarterly Technical Progress Report, AEC Unclassified Programs: July-September 1965
- Quarterly report describing progress on unclassified research programs funded by the U.S. Atomic Energy Commission during the first quarter of the 1966 fiscal year.
- Radiological Aspects of SNAPTRAN 2/10A-3 Destructive Test
- From abstract: "This report describes in detail an extensive monitoring grid used to monitor the radiological effects of the destructive excursion and subsequent release of fission products."