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  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: AEC research and development report
 Collection: Technical Report Archive and Image Library
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study
From introduction: "Presents the detailed description of a 1000 MW Electric Power Plant employing one or two Boiling Water Reactors as the steam source." digital.library.unt.edu/ark:/67531/metadc101093/
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 1
From introduction: "Summary report of the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company." digital.library.unt.edu/ark:/67531/metadc101092/
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 3
From introduction: "Contains the appendices and a complete set of drawings related to the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company for the United States Atomic Energy Commission." digital.library.unt.edu/ark:/67531/metadc101094/
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. digital.library.unt.edu/ark:/67531/metadc100653/
ABWR Design and Development Quarterly Progress Report: July 1 - September 30, 1961
Quarterly design and development progress report on the activities of the Army Boiling Water Reactor (ABWR) Program. digital.library.unt.edu/ark:/67531/metadc172544/
ABWR Design and Development Quarterly Progress Report, January 1 Through March 31, 1962
Quarterly design and development progress report on the activities of the Army Boiling Water Reactor (ABWR) Program. digital.library.unt.edu/ark:/67531/metadc172545/
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." digital.library.unt.edu/ark:/67531/metadc100242/
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development
First part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. I-ii). digital.library.unt.edu/ark:/67531/metadc172539/
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 2. Plant Conceptual Studies
Second part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. II-i). digital.library.unt.edu/ark:/67531/metadc172540/
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients
Third part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i). digital.library.unt.edu/ark:/67531/metadc172541/
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept
Fifth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i). digital.library.unt.edu/ark:/67531/metadc172543/
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." digital.library.unt.edu/ark:/67531/metadc67315/
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." digital.library.unt.edu/ark:/67531/metadc67316/
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." digital.library.unt.edu/ark:/67531/metadc67314/
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." digital.library.unt.edu/ark:/67531/metadc67313/
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. digital.library.unt.edu/ark:/67531/metadc100255/
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). digital.library.unt.edu/ark:/67531/metadc100630/
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). digital.library.unt.edu/ark:/67531/metadc100655/
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. digital.library.unt.edu/ark:/67531/metadc100650/
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. digital.library.unt.edu/ark:/67531/metadc100439/
Analytical Chemistry Division Annual Progress Report, December 31, 1961
Report presenting research and development papers from the Oak Ridge National Laboratory's Analytical Chemistry Division. digital.library.unt.edu/ark:/67531/metadc100387/
Analytical Chemistry Division Annual Progress Report for Period Ending December 31, 1959
From Summary: "78,000 analysis were performed in the Thermal Breeder Reactor Projects Analytical Chemistry Laboratory. Principal sample types, methods of analysis used, components determined, and physical measurements required are described." digital.library.unt.edu/ark:/67531/metadc100438/
Analytical Chemistry Division Annual Progress Report: for Period Ending December 31, 1962
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. digital.library.unt.edu/ark:/67531/metadc100408/
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. digital.library.unt.edu/ark:/67531/metadc100290/
Analytical Chemistry Division Annual Progress Report, May 20, 1970
Report presenting research and development papers from the Oak Ridge National Laboratory's Analytical Chemistry Division. digital.library.unt.edu/ark:/67531/metadc100440/
Analytical Chemistry Division Annual Progress Report, November 15, 1963
Report containing the ongoing research and development of the Oak Ridge National laboratory's Analytical Chemistry Division. digital.library.unt.edu/ark:/67531/metadc100338/
Analytical Chemistry Division Annual Progress Report, September 30, 1968
Report containing the ongoing research and development of the Oak Ridge National laboratory's Analytical Chemistry Division. digital.library.unt.edu/ark:/67531/metadc100470/
Annual Progress Report on Fuel Element Development for Fiscal Year 1961
Report that reviews the yearly progress made in Reactor Fuel and Materials Development Program at the Engineering Test Reactor (ETR) and Materials testing reactor (MTR). digital.library.unt.edu/ark:/67531/metadc67289/
Annual Report for 1963: Metallurgy Division
Report issued by the Argonne National Laboratory discussing work conducted by the Metallurgy Division during 1963. Annual experiments, programs, and studies are presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc170918/
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. digital.library.unt.edu/ark:/67531/metadc173354/
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. digital.library.unt.edu/ark:/67531/metadc100291/
Applied Nuclear Physics Division Annual Progress Report for Period Ending September 10, 1956
Report issued by the Oak Ridge National Laboratory discussing work completed by the Applied Nuclear Physics Division during 1956. Summaries of experiments conducted and project developments are presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc100292/
Argonne High-Flux Research Reactor: AHFR Conceptual Design Study
Report issued by the Argonne National Laboratory discussing high-flux research reactor design studies. As stated in the summary, "this report presents a reactor design to meet the needs of the basic research program at Argonne National Laboratory. The program requires some irradiation in thermal flux...and some beam experiments..." (p. 5). This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc67190/
Army Gas-Cooled Reactor Systems Program Monthly Progress Report, April 1959
Report documenting the activities of the Army Gas-Cooled Reactor Systems Program. digital.library.unt.edu/ark:/67531/metadc67293/
Army Gas-Cooled Reactor Systems Program Quarterly 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. digital.library.unt.edu/ark:/67531/metadc67300/
Army Gas-Cooled Reactor Systems Program Quarterly 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. digital.library.unt.edu/ark:/67531/metadc67299/
Army Gas-Cooled Reactor Systems Program Quarterly 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. digital.library.unt.edu/ark:/67531/metadc67301/
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. digital.library.unt.edu/ark:/67531/metadc67294/
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. digital.library.unt.edu/ark:/67531/metadc67296/
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. digital.library.unt.edu/ark:/67531/metadc67295/
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. digital.library.unt.edu/ark:/67531/metadc67297/
Army Gas-Cooled Reactor Systems Program: Semiannual Progress Report, 1 January Through 30 June 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. digital.library.unt.edu/ark:/67531/metadc67302/
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. digital.library.unt.edu/ark:/67531/metadc67298/
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. digital.library.unt.edu/ark:/67531/metadc67303/
Army Package Power Reactor APPR-1 Operating Manual and Inspection and Service Manual
Report containing basic operating instructions for the operation of the Army Package Power Reactor. This includes descriptions of the the plant's systems, operations, and safety procedures. digital.library.unt.edu/ark:/67531/metadc100961/
Army Reactors Program Annual Progress Report: for Period Ending October 31, 1962
Report summarizing ongoing nuclear work performed by the ORNL for the United States Army. digital.library.unt.edu/ark:/67531/metadc100409/
Assembly of Fifty Prototype Fuel Elements for the Experimental Gas-Cooled Reactor
Report that describes the Oak Ridge National Laboratory Experimental Gas-Cooled Reactor, problems with the procurement and assembly of its components, and its economic feasibility. digital.library.unt.edu/ark:/67531/metadc100399/
Automatic Control of T7 Tanker Boiling Water Reactor Propulsion System: Preliminary Design and Economic Evaluation
From introduction: "This report sets forth the results of a technical and economic analysis of automatic propulsion system control as a possible design improvement in the direct cycle boiling water reactor propulsion system in a T7 tanker." digital.library.unt.edu/ark:/67531/metadc101055/
Automatic Mass Spectrometer for Isotopic Analysis of Lithium
Report discussing an improvement program on lithium mass spectrometers. digital.library.unt.edu/ark:/67531/metadc173352/
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. digital.library.unt.edu/ark:/67531/metadc100623/
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