UNT Libraries Government Documents Department - 110 Matching Results
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- A Preliminary Report on the MTR Crystal Spectrometer
- Report regarding the installation and testing of a neutron crystal spectrometer. This was part of a slide show presentation.
- The Quantitative Techniques of Scintillation Spectrometry as Applied to the Calibration of Standard Sources
- Report presenting "the determination of absolute gamma emission rates for monoenergetic gamma emitters using a single-channel scintillation spectrometer. Examples are given for Cr⁵¹, Cs¹³⁷, Nb⁹⁵, and Zn⁶⁵. Sources of error are discussed and steps being taken to improve the accuracy of the method are described" (p. 1).
- Geography, Geology, and Water Resources of the National Reactor Testing Station, Idaho: Part 1 Purpose, History, and Scope of Investigations
- Central subject is the ground-water geology and hydrology of the National Reactor Testing Station, with special reference to problems of water supply, water use, and waste disposal, and to the relation of these to water supply and use on the Snake River Plain.
- Geography, Geology, and Water Resources of the National Reactor Testing Station, Idaho : Part 2, Geography and Geology
- Geologic factors in the physical environment of the National Reactor Testing Station control the amount and availability of the water supply, the methods and efficiency of obtaining water, and the behavior of waste materials that are disposed on the ground or beneath the land surface.
- Engineering Test Reactor : Engineering Design and Safeguards Report
- From abstract: "Detail and engineering drawings for the Engineering Test Reactor."
- 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.
- MTR Technical Branch Quarterly Report, Third Quarter
- Quarterly report for the technical branch of the Materials Testing Reactor of Idaho. Includes current developments and experiments.
- Scintillation Spectrometry : Gamma-Ray Spectrum Catalogue
- Report presenting a collection of gamma spectra containing samples of the response of NaI(TI) scintillation detectors to a large number of the more frequently encountered radioactive nuclides.
- A Neutron Absorption Alignment Chart
- From introduction: "Neutron absorption alignment chart for the measurement of neutron flux density."
- Startup Operation of a Production Facility for Separating Barium-140 from MTR Fuel
- Report describing "the startup operation of a batch production facility for separating and purifying barium-140 from short-cooled MTR fuel" (p. 3).
- Standard Practices for Design of MTR and ETR Safety Circuits
- Report containing notes for designing safety circuits for the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR).
- Chemical Processing Instrumentation and Control Research Program
- Report regarding the chemical processing instrumentation designs and problems at the Idaho Chemical Processing Plant.
- Summary of the Spert-I, -II, and -III reactor facilities
- Report containing "[a] brief description and design data summary of each of the SPERT Reactor Facilities is presented. Engineering, operating, and physics data are tabulated for use as basic references" (p. 3)
- Engineering Test Reactor Critical Facility Hazards Summary Report, Supplement I
- Report that "is a supplement to IDO-16332, "The Engineering Test Reactor Critical Facility Hazards Summary Report", presenting information on the conduct in the Facility of certain experiments which are expected to be operated in the Engineering Test Reactor" (p. 3).
- 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).
- 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).
- Feasibility Study, 44,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optium Power Plant) for United States Atomic Energy Commission, Idaho Operations Office
- Report that "contains a discussion of the feasibility study and cost estimates for a gas cooled, partial enriched uranium, graphite moderated power plant" (p. 3).
- Feasibility Study, Optimum Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission, Idaho Operations Office
- Report containing "a discussion of the feasibility design and cost estimates for a gas cooled, natural uranium, graphite moderated power plant optimized for minimum power cost" (p. 3).
- Feasibility Study, Optimum Partially Enriched Uranium, Gas Cooled, Graphite Moderated for United States Atomic Energy Commission, Idaho Operations Office
- Report that contains "a preliminary design and feasibility studies of gas cooled, graphite moderated, nuclear power plants" (p. 1).
- 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 describing the preliminary design of a 55,000 kW prototype of a natural uranium nuclear power plant for the United States Atomic Energy Commission. Testing of the design and potential requirements for operating the plant are included.
- 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.
- Maintenance of ETR Coolant
- Report describing the maintenance system in place for the coolant system of an Engineering Test Reactor (ETR).
- Source Strength Information for Shielding and Stack Effluent Calculations: a Standard Practices Guide
- Report presenting the curves and methods used "for determining gross fission product gamma energy in Mev/sec-watt, gross fission product beta decay in curies/sec-watt, delayed uranium fission neutrons in neutrons/sec-watt and N16 and N17 decay in photons/sec-cc of water" (p. 1).
- Supplement to Standard Practices for Design of MTR and ETR Safety Circuits
- Report that offers updated information from the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR) "experiment safety circuit manual by providing ETR power reduction curves and other information on ETR not yet available at the time the manual was issued, September 15, 1957" (p. 1).
- Standard Practices Guide for Writing Experimental Operating Manuals
- This is a sample operating manual designed to aid experimenters in writing operating manuals for MTR and ETR experiments. It contains what is felt to be the necessary information for operating a particular experiment. One of the main functions of an operating manual is to provide quick reference to material needed in an emergency. It is believed this type of manual provides the required information without an excessive amount of bulky, surplus material.
- Geography, Geology, and Water Resources of the National Reactor Testing Station, Idaho, Part 3: Hydrology and Water Resources
- This report describes the hydrology and evaluates the water resources of the ERTS, sets these in their regional perspective, and forecasts conditions and effects during future years.
- 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).
- Heat Transfer in an Annulus with Asymmetric Heating
- Report concerning the "determination of the validity of using tube flow correlations for calculating pressure drop and heat transfer characteristics in thin annuli," the "validity of using Stein's heat flux asymmetry correction for parallel planes to calculate the heat transfer in asymmetrically heated thin annuli," and the "investigation of the effects of eccentricity on pressure drop, heat transfer, and temperature distribution in concentric ring fuel elements" (p. 5).
- 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.
- Oak Ridge Site Report 30,000 KiloWatt Prototype Partially Enriched Uranium Gas Cooled, Graphite Moderated Nuclear Power Plant
- From introduction: "This report describes the selected site for a prototype nuclear plant, the reactor safety aspects for the site, the modified design of the plant, and estimate of the design and construction cost."
- Preliminary Design 30,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype of an Optimum Plant) for United States Atomic Energy Commission, Idaho Operations Office contract no. AT(10-1)-925
- Report containing the preliminary design for a nuclear reactor plant and its facilities. Includes a description of systems, safety procedures, costs, and a glossary.
- Savannah River Project Site Report: 30,000 KW Prototype Partically Enriched Uranium Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission Idaho Operations Office
- Report describing a modified prototype of a nuclear reactor that uses partially uranium-enriched fuel and is cooled by helium. The construction site, site safety aspects, and design and construction costs are included.
- 1024 Channel Time-of-Flight Analyzer for MTR Fast Chopper - Operating Manual
- Report on the principle of measuring the time-of-flight of neutrons, magnetic-core storage of detector pulses, how pulses are stored, current generator, storage cycle generator, and cathode ray oscillograph.
- Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959
- Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design criteria, and the fabrication of reactor components" (p. 1).
- In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T)
- Report documenting two in-pile loop experiments conducted at the Battelle Research Reactor-Gas Cooled Reactor (BRR-GCR). These experiments test heat transfer calculations and the behavior of the fuel element under severe thermal-cycling conditions.
- Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1959
- Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile, low-power, nuclear power plant for Military field operation.
- Preliminary Hazards Summary Report for the ML-1 Nuclear Power Plant
- From abstract: "Neutronic characteristics, the control and instrumentation system, equipment description and plant safety considerations of the ML-1 (mobile, low power) nuclear power plant. The site is described with reference to geology, climate, and population density."
- Experimental Organic Cooled Reactor : Conceptual Design
- Report presenting the design, research programs, and design objectives for an Organic-Cooled Reactor.
- Geography, Geology, and Water Resources of the National Reactor Testing Station, Idaho: Appendix 2, Basic Hydrologic Data
- Graphs and tables summarizing detailed discharge data of the Big Lost River.
- ETR Nuclear Instrumentation : Final Report
- Report regarding the primary nuclear instrumentation at the Engineering Test Reactor (ETR) and early difficulties.
- Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1959
- Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
- Proposal for an Advanced Engineering Test Reactor : ETR II
- Report containing "the results of a study which was directed at providing additional experimental loop irradiation space for the AEC-DRD testing program. It was a premise that the experiments allocated to this reactor were those that could not be accommodated in the MTR, ETR or in existing commercial test reactors" (p. 5).
- Transportability Studies : ML-1 Nuclear Power Plant
- Report that discusses programs to determine the transportability of the ML-1 nuclear power plant via railroad, tractor-trailer, and aircraft.
- The ML-1 Design Report
- From abstract: "This report describes the design of the mobile nuclear power plant which is to be the prototype of a mobile, low-powered nuclear power plant intended to furnish electrical power in remote locations."
- Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960
- Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
- In-Pile Tests of GCRE-IB Prototype Fuel Elements: Interim Report, 1958-1959
- Interim report for the Army Gas-Cooled Reactor Systems Program, discussing various tests in a project to "develop and evaluate a ceramic-core, pin-type fuel element" (p. 1).
- Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1960
- Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
- A Study of the Feasibility of a Small Scale Reprocessing Plant for the Dresden Nuclear Power Station
- Report describing the design, feasibility, and economic concerns of a small-scale reprocessing plant.
- Research and Development Studies on Waste Storage Process
- Report documenting "the determination of the thermal stability of various fission product oxides and nitrates, and an investigation of the gas phase decomposition of ruthenium tetroxide" (p. 4).
- Engineering Test Reactor Critical Facility Control System Manual
- This report consists of the description, drawings, connections, and schematics of the various control elements that make up the control system of the Engineering Test Reactor Critical Facility (ETRC).