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 Serial/Series Title: AEC research and development report
 Collection: Technical Report Archive and Image Library
10 MWe Sodium Deuterium Reactor Design Report

10 MWe Sodium Deuterium Reactor Design Report

Date: 1959
Creator: Davis, Peter J.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
11,400 KW Nuclear Power Plant Employing an Organic Moderated Reactor: Preliminary Description

11,400 KW Nuclear Power Plant Employing an Organic Moderated Reactor: Preliminary Description

Date: 1957
Creator: Wheelock, C. W.
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.
Contributing Partner: UNT Libraries Government Documents Department
200-Mwe Prototype Large SGR: Reactor Structure Design and Evaluation

200-Mwe Prototype Large SGR: Reactor Structure Design and Evaluation

Date: 1965
Creator: North American Aviation. Atomics International Division.
Description: From abstract: This document presents the reactor structure design and evaluation for a 200-Mwe prototype large SGR.
Contributing Partner: UNT Libraries Government Documents Department
300,000-KWE SGR Nuclear Power Plant of Current Technology

300,000-KWE SGR Nuclear Power Plant of Current Technology

Date: August 1, 1960
Creator: Renard, J.; Peckinpaugh, C. L. & Aronstein, R. E.
Description: Abstract: This report describes a 300,000-kwe, sodium-cooled, graphite-moderated nuclear power plant based on existing technical information.
Contributing Partner: UNT Libraries Government Documents Department
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 1

1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 1

Date: February 14, 1964
Creator: General Electric Company
Description: From introduction: "Summary report of the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company."
Contributing Partner: UNT Libraries Government Documents Department
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 2

1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 2

Date: February 14, 1964
Creator: General Electric Company
Description: From introduction: "Presents the detailed description of a 1000 MW Electric Power Plant employing one or two Boiling Water Reactors as the steam source."
Contributing Partner: UNT Libraries Government Documents Department
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 3

1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 3

Date: February 14, 1964
Creator: General Electric Company
Description: 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."
Contributing Partner: UNT Libraries Government Documents Department
6144-Channel Time-of-Flight Analyzer

6144-Channel Time-of-Flight Analyzer

Date: September 1964
Creator: Walker, R. A. & Russell, J. T.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
ABWR Design and Development Quarterly Progress Report: July 1 - September 30, 1961

ABWR Design and Development Quarterly Progress Report: July 1 - September 30, 1961

Date: October 16, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Description: Quarterly design and development progress report on the activities of the Army Boiling Water Reactor (ABWR) Program.
Contributing Partner: UNT Libraries Government Documents Department
ABWR Design and Development Quarterly Progress Report, January 1 Through March 31, 1962

ABWR Design and Development Quarterly Progress Report, January 1 Through March 31, 1962

Date: April 15, 1962
Creator: Combustion Engineering, inc. Nuclear Division.
Description: Quarterly design and development progress report on the activities of the Army Boiling Water Reactor (ABWR) Program.
Contributing Partner: UNT Libraries Government Documents Department
Addendum to the Spert IV Hazards Summary Report: Capsule Driver Core

Addendum to the Spert IV Hazards Summary Report: Capsule Driver Core

Date: February 1965
Creator: Miller, R. W.
Description: 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."
Contributing Partner: UNT Libraries Government Documents Department
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development

Date: April 1962
Creator: Combustion Engineering, inc. Nuclear Division.
Description: 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).
Contributing Partner: UNT Libraries Government Documents Department
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 2. Plant Conceptual Studies

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 2. Plant Conceptual Studies

Date: March 1962
Creator: Combustion Engineering, inc. Nuclear Division.
Description: 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).
Contributing Partner: UNT Libraries Government Documents Department
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients

Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Description: 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).
Contributing Partner: UNT Libraries Government Documents Department
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept

Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Description: 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).
Contributing Partner: UNT Libraries Government Documents Department
An Advanced Sodium-Graphite Reactor Nuclear Power Plant

An Advanced Sodium-Graphite Reactor Nuclear Power Plant

Date: March 15, 1960
Creator: Churchill, J. R. & Renard, J.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Advanced Test Reactor Burnout Heat Transfer Tests

Advanced Test Reactor Burnout Heat Transfer Tests

Date: January 1964
Creator: Croft, M. W.
Description: From abstract: "Results of burnout test to determine the limiting heat flux in a simulated Advanced Test Reactor fuel element channel."
Contributing Partner: UNT Libraries Government Documents Department
Advanced Test Reactor: Final Shielding Design Report

Advanced Test Reactor: Final Shielding Design Report

Date: December 1963
Creator: Howard, J. O.
Description: 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."
Contributing Partner: UNT Libraries Government Documents Department
Advanced Test Reactor Servo Regulator Rod Test Program

Advanced Test Reactor Servo Regulator Rod Test Program

Date: February 1964
Creator: Pickett, R. T.
Description: 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."
Contributing Partner: UNT Libraries Government Documents Department
Advanced Test Reactor Turbo Report

Advanced Test Reactor Turbo Report

Date: January 1964
Creator: Turner, Robert A.
Description: 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."
Contributing Partner: UNT Libraries Government Documents Department
Aircraft Reactor Test Removal and Disassembly

Aircraft Reactor Test Removal and Disassembly

Date: 1960?
Creator: Abbatiello, A. A. & McQuilkin, F. R.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel

An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel

Date: July 1963
Creator: Jackson, C. N., Jr.
Description: 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).
Contributing Partner: UNT Libraries Government Documents Department
Analog Computer Simulation of a Pulsed Extraction Column

Analog Computer Simulation of a Pulsed Extraction Column

Date: September 1964
Creator: Benham, R. D. & Wilburn, N. P.
Description: 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).
Contributing Partner: UNT Libraries Government Documents Department
Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model

Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model

Date: September 1, 1964
Creator: Swanson, C. D.; Coughren, K. D.; Dionne, P. J. & Thieme, G. G.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
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