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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
10 MWe Sodium Deuterium Reactor Design Report
From foreword: This report describes the goal of the overall SDR program to demonstrate the commercial generation of electrical power using a sodium-cooled reactor. digital.library.unt.edu/ark:/67531/metadc502675/
11,400 KW Nuclear Power Plant Employing an Organic Moderated Reactor: Preliminary Description
Abstract: The preliminary design is described for a small electric-power-generating plant powered by an organic moderated reactor. System and component requirements are discussed and possible design configurations and equipment are described. digital.library.unt.edu/ark:/67531/metadc853023/
200-Mwe Prototype Large SGR: Reactor Structure Design and Evaluation
From abstract: This document presents the reactor structure design and evaluation for a 200-Mwe prototype large SGR. digital.library.unt.edu/ark:/67531/metadc860802/
300,000-KWE SGR Nuclear Power Plant of Current Technology
Abstract: This report describes a 300,000-kwe, sodium-cooled, graphite-moderated nuclear power plant based on existing technical information. digital.library.unt.edu/ark:/67531/metadc853112/
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 2
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 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/
An Advanced Sodium-Graphite Reactor Nuclear Power Plant
Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency. digital.library.unt.edu/ark:/67531/metadc853018/
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 Models for HNPF Control and Protection Studies
Abstract: This report, intended as a working document, contains analytic representations and analog models of the Hallam Nuclear Power Facility as used in studies of the Control and Protection Systems. digital.library.unt.edu/ark:/67531/metadc304030/
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 Stresses in Bellows
Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows. digital.library.unt.edu/ark:/67531/metadc853001/
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 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 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, 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/
Application of Fast Neutron Removal Theory to the Calculation of Thermal Neutron Flux Distributions in Reactor Shields
Abstract: A calculational method is presented which may be used to determine fast and thermal neutron flux distributions at deep neutron penetrations in hydrogenous shields. digital.library.unt.edu/ark:/67531/metadc853082/
Application of Nuclear Power Plants (SNAP Units) to the Manned Orbiting Research Laboratory (MORL)
Abstract: This report describes in detail two designs of a nominal 6-kwe Nuclear Power Plant (NPP), one using thermoelectrics for power conversion and the other using the Mercury-Rankine cycle NPP. digital.library.unt.edu/ark:/67531/metadc860779/
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
Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design criteria, and the fabrication of reactor components" (p. 1). digital.library.unt.edu/ark:/67531/metadc67293/
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: 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 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. digital.library.unt.edu/ark:/67531/metadc67300/
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. digital.library.unt.edu/ark:/67531/metadc67301/
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. digital.library.unt.edu/ark:/67531/metadc67302/
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 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: 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: 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, 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/
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