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  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: Atomic Energy Commission Reports
 Collection: Technical Report Archive and Image Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System
Final design for the 30 megawatt intermediate heat exchanger and steam generator. digital.library.unt.edu/ark:/67531/metadc100973/
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis
Chemical engineering analysis and stress analysis for design of the 3 megawatt intermediate heat exchanger and steam generator for service with a liquid sodium heat transfer fluid. digital.library.unt.edu/ark:/67531/metadc100974/
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures
Operation and maintenance procedures for 30 megawatt heat exchanger and steam generator for sodium cooled reactor system. digital.library.unt.edu/ark:/67531/metadc100975/
100-Ton Test at Trinity: Report on Earth Velocity Measurements
Apparatus, field layout, miscellaneous testing, and the method of analysis of a 100-ton test at Trinity. digital.library.unt.edu/ark:/67531/metadc100797/
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/
Accidental Radiation Excursion at the Y-12 Plant, June 16, 1958: Final Report
This report describes the circumstances leading to the accident, attempts to reconstruct the nuclear reactivity conditions, and reviews the dosimetric means and results which were used to help determine the exposure of affected employees. digital.library.unt.edu/ark:/67531/metadc173360/
An Addendum to a Parametric Study of the Gas-Cooled Reactor Concept
From introduction: "This report provides background information regarding the study results presented in the first volume of this report and provides information resulting from the studies made on the gas cooled reactor concept." digital.library.unt.edu/ark:/67531/metadc100571/
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 4. Steam Driven Coolant Pumps
Fourth 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/metadc172542/
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: 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/
Aerial Radiological Monitoring System
From abstract: "This report describes the Aerial Radiological Measuring System (ARMS-II) operated by EG&G, Inc., for the Division of Biology and Medicine, U. S. Atomic Energy Commission." digital.library.unt.edu/ark:/67531/metadc172722/
An Air-Borne Densitometer for Smoke Concentration Measurements
A simple, light-weight, split beam optical smoke densitometer is described. digital.library.unt.edu/ark:/67531/metadc100765/
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, Beta, Gamma Hand and Shoe Counter - Model 2
Experimental combination hand and shoe counter redesign as a compact, simplified, register readout instrument no larger than the present Five-Fold called Model 2. digital.library.unt.edu/ark:/67531/metadc100570/
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/
Aluminum Titanate as a Ceramic Material
A report on using aluminum titanate as a ceramic materiel. digital.library.unt.edu/ark:/67531/metadc100799/
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/
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. digital.library.unt.edu/ark:/67531/metadc101088/
Analysis of Meteorological Tower Data, April 1950 - March 1952, Brookhaven National Laboratory
Report issued by the Brookhaven National Laboratory discussing data collected from two BNL meteorological towers. As stated in the introduction, "results are presented in graphic form rather than tabular form" (p. 1). This report includes tables, maps, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc170954/
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/
Analytical Studies of Transient Effect in Fast Reactor Fuels: [Part] 1
From abstract: "An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined and possible mechanisms of failure are analyzed." digital.library.unt.edu/ark:/67531/metadc101103/
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/
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. digital.library.unt.edu/ark:/67531/metadc67309/
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). digital.library.unt.edu/ark:/67531/metadc67251/
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/
Application of Photogrammetric Techniques for Environmental Surveillance of Amchitka Island, Alaska, Annual Progress Report, July 1, 1969 - June 30, 1970
Report concerning surveys made to determine the abundance and distribution of otters at Amchitka Island, Alaska, as well to document the effects of an underground nuclear reactor. digital.library.unt.edu/ark:/67531/metadc100825/
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/
APPR-1: Design, Construction and Operation
"This document includes papers covering technical problems involved in the design, construction and operation of the APPR-1" (p. 4). digital.library.unt.edu/ark:/67531/metadc100959/
APPR-1 Research and Development Program. Design Analysis for Flow and Temperature Measurement Program, Task No. 5
From objectives: "To establish, by literature search, analysis and design, the engineering and fabrication requirements for modifying reactor components and developing and installing the necessary instrumentation to carry out a fuel temperature and flow measurement experimental program." digital.library.unt.edu/ark:/67531/metadc100964/
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