Technical Report Archive & Image Library (TRAIL) - 415 Matching Results
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- 1000-MWe LMFBR Follow-On Study, Task I Report: Volume 1
- From introduction: "The objective of this study is to provide information that will assist the Atomic Energy Commission in furthering the National Liquid Metal Fast Breeder Reactor (LMFBR) Program. We plan to accomplish this end, in part, by extending the original studies to include system and component design and parametric evaluations of the nuclear steam supply system and its related systems and subsystems based on an estimation of the state of technology in 1980."
- 1000-MWe LMFBR Follow-On Study, Task I Report: Volume 2, Concept I System Description
- From introduction: "This report has been prepared in conjunction with the Liquid Metal Fast Breeder Reactor (LMFBR) Follow-On Study. It is the Concept I description of Task I as outlined by Argonne National Laboratory (ANL) in Appendix C of their Follow-On Study Program."
- 1000-MWe LMFBR Follow-On Study, Task I Report: Volume 5, Concept IV System Description
- From introduction: "The last of four designs to be developed by Babcock & Wilcox (B&W), Concept IV observes ground rules established under the LMFBR Follow-On Program and is based on the estimated state of technology in 1980."
- [3D Viewer]
- Black cardboard viewer with plastic lenses, "for printed stereo photographs." It has scored portions and instructions for folding the cardboard to create a standing viewer to look through the lenses and keep the image at a distance.
- 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.
- 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."
- Advanced Pressurized Water Reactor Study [Part 1, Supplement]: Phase 2--A Report
- From introduction: This report details the progress of the Advanced Pressurized Water Reactor Study.
- Advanced Test Reactor Burnout Heat Transfer Tests
- From abstract: "Results of burnout test to determine the limiting heat flux in a simulated Advanced Test Reactor fuel element channel."
- 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."
- 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."
- Aerospace Nuclear Safety: October 1 - 4, 1963
- Proceedings on aerospace nuclear safety.
- Aircraft Reactor Test Removal and Disassembly
- Report documenting the dissection of a reactor called the Aircraft Reactor Test (ART). Includes the removal of the reactor from its test cell, component removal, and plans for a for a disassembly building facility.
- 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).
- 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).
- 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.
- Analysis of Failure of Type 304 Stainless Steel Clad Swaged Powder Fuel Assembly
- From introduction: "The purpose of this report is to describe the observations made during the post-irradiation examination of HPD-2S, and to discuss possible modes of failure.
- Analytical Chemistry Division Annual Progress Report, December 31, 1960
- Report presenting research and development papers from the Oak Ridge National Laboratory's Analytical Chemistry Division.
- 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.
- Analytical Chemistry in Nuclear Reactor Technology: 1961
- "An Automated Spectrograph has been developed for the analyses of beryllium contained on filter paper discs. With this instrument, unattended analyses can be carried out on a number of samples following simple sample preparation. Filter paper discs representing beryllium in the atmosphere as well as those used for evaluating surface contamination are accommodated. Included in the uniting are an automatic electrode changer, analytical gap servo control, spectrograph, signal detector, and computer and readout system. The performance of the instrument in the range of 0.5 to 40 mg of beryllium is discussed."
- The Application of Data Processing Techniques to a Maintenance Work Control Program
- Description of a data collection and reporting system which was devised and installed in the Union Carbide Nuclear Company's Y-12 Plant Maintenance Division.
- 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.
- Argonne National Laboratory Metallurgy Division Annual Report: 1963
- Annual report issued by the Argonne National Laboratory discussing work conducted by the Metallurgy Division during 1963 including progress related to experiments, programs, and studies. This report includes tables, illustrations, and photographs.
- 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.
- 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.
- 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.
- Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 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.
- 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.
- 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.
- 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.
- 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.
- 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.
- Gas-Cooled Reactor Project Semiannual Progress Report: March 1964
- Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project. From summary: "A study was made of the effect of the energy of extraneous source neutrons on the amplitudes of higher modes in the flux distribution of a subcritical reactor."
- Army Reactors Program Annual Progress Report: 1962
- Report summarizing ongoing nuclear work performed by the ORNL for the United States Army.
- Automatic Mass Spectrometer for Isotopic Analysis of Lithium
- Report discussing an improvement program on lithium mass spectrometers.
- 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.
- Beta-Gamma Dose Rates from U232 in U233
- This report defines in detail the source of the dose rate of U233 and describes a method by which they may be predicted.
- Boiling Water Reactor Study [Part 1, Supplement]: Refinements of 306 Mw Power Reactor Conceptual Design
- From introduction: The objectives of the study are to review the designs and costs of the 306 mw selected BWR and to determine the effect of refinements on plant performance and costs.
- Boiling Water Reactor Study [Part 2, Supplement]: Separate Studies
- From summary and conclusions: This study has been made to determine the feasibility of installing reheat steam facilities in conjunction with the selected 306-mw boiling water nuclear power plant.
- Boiling Water Reactor Study [Part 4]: 100 Mw Boiling Water Reactor Conceptual Design
- From introduction: This report sets forth the results of a study of a 100-mw dual cycle boiling water reactor, nuclear power plant.
- 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.
- 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.
- Chemical Coolants for Machining Uranium in the Presence of Trace Amounts of Chloride
- Discussion of laboratory tests to reduce uranium corrosion.
- Chemical Technology Division Annual Progress Report, August 31, 1960
- Report documenting the ongoing research of the Oak Ridge National Laboratory's Chemical Technology Division. This report includes tables, diagrams, graphs, and articles related to chemical technology.
- 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.
- 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.
- 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.
- Chemical Technology Division Annual Progress Report, May 31, 1961
- Report documenting the ongoing research and developments of the Chemical Technology Division of the Oak Ridge National Laboratory.
- Chromosomal Aberrations in a Natural Population of Chironomus Tentans Exposed to Chronic Low-Level Environmental Radiation
- From introduction: "Cytological examinations of the irradiated and some unirradiated populations in the radioactive sediments of White Oak Creek and the Clinch River were made."
- Civilian Power Reactor Program, Part 3: Status Report on Fast Reactors as of 1959
- From summary: The objective of the fast reactor program is to achieve economic power while burning a large fraction of the source uranium.