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  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: Atomic Energy Commission Reports
 Collection: Technical Report Archive and Image Library
Accidental Radiation Excursion at the Y-12 Plant, June 16, 1958: Final Report

Accidental Radiation Excursion at the Y-12 Plant, June 16, 1958: Final Report

Date: September 12, 1958
Creator: Patton, F. S.; Bailey, J. C.; Callihan, A. D.; Googin, J. M.; Jasny, G. R.; McAlduff, H. J. et al.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
An Addendum to a Parametric Study of the Gas-Cooled Reactor Concept

An Addendum to a Parametric Study of the Gas-Cooled Reactor Concept

Date: March 1, 1958
Creator: unknown
Description: 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."
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 4. Steam Driven Coolant Pumps

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 4. Steam Driven Coolant Pumps

Date: October 23, 1961
Creator: Combustion Engineering, Inc. Nuclear Division.
Description: 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).
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
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