Technical Report Archive & Image Library (TRAIL) - 110 Matching Results
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- 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.
- 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
- 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 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.
- 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).
- 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."
- 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.
- 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.
- 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).
- 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.
- 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."
- Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1964
- Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
- 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).
- 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."
- Zirconium Processing Capability of the Idaho Chemical Processing Plant
- Report discussing a hydrofluoric acid dissolution process that allows the processing of zirconium- or Zircaloy-clad zirconium-uranium fuels.
- Full Power and Limited Endurance Test of the ML-1 Nuclear Power Plant (ANSOP 16625A)
- Report presenting "[t]he results of performance analyses of the ML-1 nuclear power plant based on the test data obtained during ANSOP 16625A" (p. v).
- Scintillation Spectrometry Gamma-Ray Catalogue: Volume 2
- Gamma-Ray Spectrum diagrams.
- Fundamentals in the Operation of Nuclear Test Reactors: Volume 3 Engineering Test Design and Operation
- Engineering test reactor design and operation.
- In-Pile Test of Prototype ML-1 Fuel Elements
- Report documenting the testing of prototype fuel elements used in a mobile nuclear power plant. Includes descriptions and evaluations of the test.
- 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."
- 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."
- 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.
- Topic: a Fortran Program for Calculating Transport of Particles in Cylinders
- Report discussing the use of TOPIC Sn computer code in the attempt to find a solution to the Boltzmann transport equation.
- 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."
- Results of ATR Sample Fuel Plate Irradiation Experiment
- From abstract: "Fuel materials proposed for use in the Advanced Test Reactor were evaluated."
- 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."
- 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."
- 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."
- ICPP Waste Calcining Facility : Safety Analysis Report
- Report documenting a study "made of the radiological hazards associated with operation of the ICPP Waste Calcination Facility" and contains "[d]etails of the safety analysis and extensive information on the process, equipment, and operation procedures" (p. iii). Each section has its own pagination.
- Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1963
- Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
- 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.
- 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.
- 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.
- EDP Procedures in Technical Library Operations
- Systems for circulation control, book ordering, journal renewal, printing a book catalog, preparing monthly acquisitions lists.
- 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."
- 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]).
- 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.
- 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."
- Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1963
- Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
- 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."
- High-Temperature Irradiation of UOâ‚‚-BeO Bodies
- From introduction: "Irradiation experiment performed to simulate burnup data under close to reactor temperatures."
- Terminal Report : Conceptual Study of a System for Radioactive Demonstration of the Chop-Leach Process
- Report that summarizes the design work of the radioactive chop-leach demonstration at the Idaho Chemical Processing Plant presented in two parts.
- 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.
- 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.
- Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1962
- 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.
- 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.
- Pilot Plant Development Studies of a Continuous Process for Recovering Uranium from Nichrome Fuels
- Report documenting a process for recovering uranium from nichrome fuels (HTRE). This is accomplished by dissipating the fuel into a mixture of HCl-HNO3, stripping away chlorine ions with HN03, and recovering the uranium via tributyl phosphate solvent extraction.