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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.
Date:
1959
Creator:
Davis, Peter J.
System:
The UNT Digital Library
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.
Date:
1957
Creator:
Wheelock, C. W.
System:
The UNT Digital Library
A 37,500 KW Power Reactor with Competitive Possibilities
The following report follows the study on economics of nuclear power generation using a light water reactor.
Date:
February 26, 1954
Creator:
Thompson, W. I. & Cohen, Karl
System:
The UNT Digital Library
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.
Date:
1965
Creator:
North American Aviation. Atomics International Division.
System:
The UNT Digital Library
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.
Date:
August 1, 1960
Creator:
Renard, J.; Peckinpaugh, C. L. & Aronstein, R. E.
System:
The UNT Digital Library
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."
Date:
February 14, 1964
Creator:
General Electric Company
System:
The UNT Digital Library
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."
Date:
February 14, 1964
Creator:
General Electric Company
System:
The UNT Digital Library
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."
Date:
February 14, 1964
Creator:
General Electric Company
System:
The UNT Digital Library
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.
Date:
September 1964
Creator:
Walker, R. A. & Russell, J. T.
System:
The UNT Digital Library
ABWR: PL-2 Design Report
From preface: This report satisfies the quarterly progress report requirements for PL-1 and PL-2 plant design work for the period ending September 30, 1960 At present time a SL-1 Core 2 is under construction. This is a replacement core for SL-1 (ALPR) and will be identical to a PL-2 core; a PL condenser is under test at the SL-1 facility; final construction plans for PL components and modules which are not site sensitive will be completed in March 1961.
Date:
October 15, 1960
Creator:
Combustion Engineering, inc. Nuclear Division.
System:
The UNT Digital Library
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.
Date:
October 16, 1961
Creator:
Combustion Engineering, inc. Nuclear Division.
System:
The UNT Digital Library
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.
Date:
April 15, 1962
Creator:
Combustion Engineering, inc. Nuclear Division.
System:
The UNT Digital Library
Accurate Nuclear Fuel Burnup Analyses; First Quarterly Report, (December 1961 - February 1962)
The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date:
April 1, 1962
Creator:
Rider, B. F.
System:
The UNT Digital Library
Accurate Nuclear Fuel Burnup Analyses; Second Quarterly Progress Report, (March - May 1962)
The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date:
July 1, 1962
Creator:
Rider, B. F.
System:
The UNT Digital Library
Accurate Nuclear Fuel Burnup Analysis Quarterly Progress Report: Seventh Quarter, June 1963 - August 1963
Quarterly progress report on Accurate Nuclear Fuel Burnup Analysis project.
Date:
September 1, 1963
Creator:
Rider, B. F.; Ruiz, C. P.; Peterson, J. P., Jr.; Luke, P. S., Jr. & Smith, F. R.
System:
The UNT Digital Library
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."
Date:
February 1965
Creator:
Miller, R. W.; McCardell, Richard K. & Lagier, T. F.
System:
The UNT Digital Library
Adiabatic Injection
From introduction comments: The present analysis is intended to examine the relations for "adiabatic" injection in general from a different point of view.
Date:
September 22, 1955
Creator:
Linlor, William I., 1915-
System:
The UNT Digital Library
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).
Date:
April 1962
Creator:
Combustion Engineering, inc. Nuclear Division.
System:
The UNT Digital Library
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).
Date:
March 1962
Creator:
Combustion Engineering, inc. Nuclear Division.
System:
The UNT Digital Library
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).
Date:
October 23, 1961
Creator:
Combustion Engineering, inc. Nuclear Division.
System:
The UNT Digital Library
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).
Date:
October 23, 1961
Creator:
Combustion Engineering, inc. Nuclear Division.
System:
The UNT Digital Library
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.
Date:
March 15, 1960
Creator:
Churchill, J. R. & Renard, J.
System:
The UNT Digital Library
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."
Date:
January 1964
Creator:
Croft, M. W.
System:
The UNT Digital Library
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."
Date:
December 1963
Creator:
Howard, J. O. & Jacks, G. M.
System:
The UNT Digital Library