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- National Uranium Resource Evaluation, Athens Quadrangle, Georgia and South Carolina, Appendix D: Petrologic Reports, Petrographic Descriptions, Heavy Mineral Analyses, X-Ray Mineral Identification, Uranium Mineral Analyses
- Appendix containing the petrologic reports, descriptions, and mineral analyses recorded for the studies of the Athens quadrangle.
- National Uranium Resource Evaluation, Athens Quadrangle, Georgia and South Carolina, Appendix C: Uranium-Occurrence Reports
- This appendix records uranium occurrences found in the Athens quadrangle, Georgia.
- National Uranium Resource Evaluation, Athens Quadrangle, Georgia and South Carolina: Appendix E: Track Etch Survey Results and Statistics
- Discussing Track Etch survey results and statistics in the Athens Quadrangle
- Rice Lake Quadrangle, Wisconsin
- The following report presents the hydrogeochemical and stream sediment and aerial radiometric reconnaissance survey data that were evaluated in uranium resources of the Rice Lake Quadrangle, Wisconsin.
- National Uranium Resource Evaluation, Athens Quadrangle, Georgia and South Carolina
- The following report documents the detailed geologic and radiometric investigations that were conducted in the Athens quadrangle in Georgia and South Carolina.
- Design for a Fast Flux Liquid Metal Loop in the Advanced Test Reactor
- The purpose of this document is to present criteria for the Titles I and II design of the Fast Flux Loop Facility which is to be a part of the Advanced Test Reactor. This facility is to be used for irradiation of fast reactor assemblies under simulated fast reactor operating conditions.
- 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.
- 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.
- 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.
- Materials Testing Reactor-Engineering Test Reactor Technical Branches Quarterly Report: October 1 - December 31, 1963
- From summary: "Reactor fuel material consisting of U3Si particles embedded in an aluminum matrix have been examined with an electron microprobe to determine reaction between fuel particles and matrix. Partial reaction was observed with no observable tendency for the uranium or silicon to diffuse outward into the matrix.
- 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).
- Gamma-Ray Spectrometry of Neutron-Deficient Isotopes: Annual Progress Report, March 1964
- From abstract: "The objective of this program is to produce a set of pulse-height spectra representing the response of a standard gamma-ray scintillation spectrometer to radiations emitted in the decay of neutron-deficient nuclides."
- Gamma-Ray Spectrometry of Neutron-Deficient Isotopes: Annual Progress Report, November 1964
- Progress report discussing the activities in "a program of studies of nutron-deficient isotopes using the techniques of gamma-ray spectroscopy" (abstract).
- Fundamentals in the Operation of Nuclear Test Reactors: Volume 2, Materials Testing Reactor Design and Operation
- Second volume of reports on the operation of nuclear test reactors. It includes six chapters: engineering description fo the materials testing reactor, reactor control components and instrumentation, reactor control circuitry, reactor operation, reactor shutdown and tank work, and supplemental facilities at the materials testing reactor.
- Gamma-Ray Spectrometry of Neutron-Deficient Isotopes: Annual Progress Report, June 1966
- Progress report discussing the activities in "a program of studies of nutron-deficient nuclides using the techniques of gamma-ray spectroscopy" (abstract).
- An Engineering Test Program to Investigate a Loss of Coolant Accident
- From preface: "The purpose of this report is to present an engineering test program for investigating a loss of coolant accident for a pressurized water-cooled and moderated reactor system."
- 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.
- Television System Study for Accident Recovery : Phase I
- From abstract: "A previous study of equipment necessary for clean-up following a nuclear accident indicated a need for a portable television system capable of operating in hazardous environments during recovery operations. A system to accomplish this is described and justified in this study."
- EOCR Control Rod and Driver Fuel Hydraulic Tests
- Report discussing the results of experiments on an EOCR prototype control rod, control rod drive, and driver fuel assembly that were extensively tested in 500 deg F Santowax and 132 deg F water. These tests not only established the operating characteristics of these assemblies but also revealed a number of deficiencies in the various components. It includes descriptions of the control rod, control rod drive, and driver fuel assembly together with descriptions of their method of operation.
- EDP Procedures in Technical Library Operations
- Systems for circulation control, book ordering, journal renewal, printing a book catalog, preparing monthly acquisitions lists.
- Results of ATR Sample Fuel Plate Irradiation Experiment
- From abstract: "Fuel materials proposed for use in the Advanced Test Reactor were evaluated."
- 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."
- 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."
- Advanced Test Reactor Turbo Report
- From abstract: "The time-dependent behavior of the Advanced Test Reactor was calculated by the Babcock & Wilcox Company on the Philco 2000 computer, using the Turbo depletion program."
- 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).
- 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."
- 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.
- 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."
- High-Temperature Irradiation of UOâ‚‚-BeO Bodies
- From introduction: "Irradiation experiment performed to simulate burnup data under close to reactor temperatures."
- STEP Project Quarterly Technical Report: January-June 1964
- Report regarding the Safety Test Engineering Program (STEP), the transient and destructive testing of the aerospace SNAP 10A/2 reactor, and the evaluation of the results of these tests.
- Hydrology of Subsurface Waste Disposal, National Reactor Testing Station, Idaho : Annual Progress Report, 1963
- From introduction: "The present report indicates additional preliminary progress in the interpretation of the geology of the area on the basis of preliminary gravity and magnetic surveys and sketches the progress made in operational phases of the study of the hydrology of waste disposal."
- The Design of a Dynamic Corrosion and Chemical Control Test Loop and Preliminary Out-of-Pile Test Results
- From abstract: "This report describes the overall loop design and the means by which this design was developed. These include critical facility measurements, analog computer calculations, hydraulic and heat transfer computations, and the construction and operation of an out-of-pile mock-up loop to determine the dynamic characteristics of the loop."
- Safety Analysis Report : Snaptran 2/10A-1 Safety Tests
- From summary: "The report contains descriptions and discussions on nuclear safety testing."
- Evaluation of Radiation Stabilizers for Terphenyl by High-Temperature Electron Irradiation
- From summary: "Experiments to determine effectiveness of additives to reduce radiolytic damage to a mixture of isometric terphenyls in which 93 separate compounds were evaluated."
- Fundamentals in the Operation of Nuclear Test Reactors: Volume 3 Engineering Test Design and Operation
- Engineering test reactor design and operation.
- Scintillation Spectrometry Gamma-Ray Catalogue: Volume 2
- Gamma-Ray Spectrum diagrams.
- Routine Testing and Calibration Procedures for Multichannel Pulse Analyzers and Gamma-Ray Spectrometers
- Report describing the results of laboratory tests with procedures for calibration of equipment and performance requirements.
- 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.
- 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.
- Hydrology of Waste Disposal, National Reactor Testing Station, Idaho: Annual Progress Report, 1962
- Report describing investigations to determine the effect of underground disposal of liquid radioactive waste upon the regional groundwater resources.
- Completion Report for Observation Wells 1 through 49, 51, 54, 55, 56, 80, and 81 at the National Reactor Testing Station, Idaho
- From introduction: "This report presents lithologic and geophysical logs and construction data for NRTS research observation wells."
- Engineering Test Reactor : Engineering Design and Safeguards Report
- From abstract: "Detail and engineering drawings for the Engineering Test Reactor."
- Advanced Test Reactor: Final Shielding Design Report
- From abstract: "This report has been prepared as a design reference document describing the calculation methods and engineering results for shielding analysis work done during the design of the Advanced Test Reactor."
- 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."
- Summary Report of Design Criteria for a Thermal Flux Liquid Metal Package Loop in the Advanced Test Reactor
- From introduction: "Report summarizing all work completed during the preparation of design criteria for thermal flux loop."
- Advanced Test Reactor Servo Regulator Rod Test Program
- From abstract: "Verify rod mechanism characteristics reported by the United Shoe Machinery Corporation, demonstrate that rod mechanism characteristics were compatible with reactor kinetics and that over-all reactor system behavior was stable, and to recommend system modifications needed for satisfactory performance."
- A Neutron Absorption Alignment Chart
- From introduction: "Neutron absorption alignment chart for the measurement of neutron flux density."
- Final Summary Report of the Gas-Cooled Reactor Experiment-1
- Report describing the Gas-Cooled Reactor test facility, its ongoing testing and evaluations of a test reactor, and its operating conditions and characteristics.
- 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.
- 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).