Prestressed Concrete Reactor Vessel Model 1 (open access)

Prestressed Concrete Reactor Vessel Model 1

From introduction: The goal of engineers associated with nuclear power plants is the achievement of safe plants with low generating costs.One possible means of lowering costs is to increase the power generating capability for a single generating unit. To accomplish this, the sizes of nuclear reactors have been increased.
Date: October 25, 1966
Creator: unknown
System: The UNT Digital Library
Design, Construction, and Initial Operation of General Atomic In-Pile Loop (open access)

Design, Construction, and Initial Operation of General Atomic In-Pile Loop

From preface: To test the HTGR fuel-element design under environmental conditions of radiation, temperature, and pressure that approximate those in the Peach Bottom core and to test the operability of a dynamic system containing a vented graphite-clad fuel element.
Date: February 15, 1965
Creator: Simon, R. H.
System: The UNT Digital Library
Design Study Report for TARGET: A 1000-Mw(e) High-Temperature Gas-Cooled Reactor (open access)

Design Study Report for TARGET: A 1000-Mw(e) High-Temperature Gas-Cooled Reactor

Introduction: The scope of work for the contract stated that General Atomic was to undertake a preliminary design study and related exploratory development program for a 1000-Mw(e), advanced, gas-cooled reactor.
Date: November 1964
Creator: General Dynamics Corporation. General Atomic Division. John Jay Hopkins Laboratory for Pure and Applied Science
System: The UNT Digital Library
Integral Neutron Thermalization, Annual Summary Report: October 1963-September 1964 (open access)

Integral Neutron Thermalization, Annual Summary Report: October 1963-September 1964

From introduction: This report contains D2O spectral investigations, measurements of scattering angular distributions, BeO spectral measurements, studies of space dependent problems, theoretical studies, and preliminary studies of fast neutron shielding.
Date: October 15, 1964
Creator: Beyster, J. R.; Brown, J. R.; Corngold, N.; Honeck, H. C.; Houston, D. H.; Joanou, G. D. et al.
System: The UNT Digital Library
Investigation of Turbocirculator for Target, a 1000-Mw(e) Reactor: Summary Report (open access)

Investigation of Turbocirculator for Target, a 1000-Mw(e) Reactor: Summary Report

The present study was undertaken for the purpose of determining the feasibility, establishing the required development program, and estimating the cost of a turbocirculator to provide the pumping power for a 1000-Mw(e) high-temperature gas-cooled reactor power plant as part of the TARGET program. This necessitated preliminary design of the turbocirculator in conjunction with the reactor power plant as well as the investigation of methods for the optimization of the turbocirculator and for its development. This study was carried out in sufficient detail to fix the methods required to resolve the problems that would be encountered during the course of a prototype program resulting in a turbocirculator for the TARGET power plant.
Date: September 28, 1964
Creator: Yampolsky, J.; Barbat, V.; Berman, H.; Cavallaro, L.; Ross, F. & Todt, L.
System: The UNT Digital Library
Integral Neutron Thermalization, Annual Summary Report: October 1962-September 1963 (open access)

Integral Neutron Thermalization, Annual Summary Report: October 1962-September 1963

Introduction: This report describes the Integral Neutron Thermalization activities at General Atomic from October 1, 1962, through September 30, 1963.
Date: January 24, 1964
Creator: Beyster, J. R.; Brown, J. R.; Koppel, J. U.; Neill, J. M.; Russell, J. L., Jr.; Trimble, G. D. et al.
System: The UNT Digital Library
Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: April-June 1961 (open access)

Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: April-June 1961

Quarterly report discussing activities of the Maritime Gas-Cooled Reactor (MGCR) Program and the progress of the Program in developing a nuclear-powered marine propulsion system utilizing a high-temperature, gas-cooled nuclear reactor, close-cycle gas-turbine power plant.
Date: July 31, 1963
Creator: unknown
System: The UNT Digital Library
Maritime Gas-Cooled Reactor Program: Suggested Values for the Partial Cross Sections of U²³⁵ for Use in the Neutronic Analysis of Thermal and Intermediate Reactors (open access)

Maritime Gas-Cooled Reactor Program: Suggested Values for the Partial Cross Sections of U²³⁵ for Use in the Neutronic Analysis of Thermal and Intermediate Reactors

From abstract: In this report a consistent set of U-235 partial cross sections for use in the analysis of thermal or intermediate reactor systems has been provided.
Date: July 17, 1961
Creator: Goodjohn, A. J. & Wikner, N. F.
System: The UNT Digital Library
Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: October-December 1960 (open access)

Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: October-December 1960

Quarterly report discussing activities of the Maritime Gas-Cooled Reactor (MGCR) Program and the progress of the Program in developing a nuclear-powered marine propulsion system utilizing a high-temperature, gas-cooled nuclear reactor, close-cycle gas-turbine power plant.
Date: 1961?
Creator: unknown
System: The UNT Digital Library
Maritime Gas-Cooled Reactor Program: MGCR Prototype Preliminary Design, Volume 1 (open access)

Maritime Gas-Cooled Reactor Program: MGCR Prototype Preliminary Design, Volume 1

From preface: This report presents the status of design of the MGCR prototype plant as of July 1, 1960.
Date: December 9, 1960
Creator: General Dynamics Corporation
System: The UNT Digital Library
Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: January-March 1960 (open access)

Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: January-March 1960

Quarterly report discussing activities of the Maritime Gas-Cooled Reactor (MGCR) Program and the progress of the Program in developing a nuclear-powered marine propulsion system utilizing a high-temperature, gas-cooled nuclear reactor, close-cycle gas-turbine power plant.
Date: March 31, 1960
Creator: unknown
System: The UNT Digital Library
Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: October-December 1959 (open access)

Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: October-December 1959

Quarterly report discussing activities of the Maritime Gas-Cooled Reactor (MGCR) Program and the progress of the Program in developing a nuclear-powered marine propulsion system utilizing a high-temperature, gas-cooled nuclear reactor, close-cycle gas-turbine power plant.
Date: 1960?
Creator: unknown
System: The UNT Digital Library
Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: April-June 1960 (open access)

Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: April-June 1960

Quarterly report discussing activities of the Maritime Gas-Cooled Reactor (MGCR) Program and the progress of the Program in developing a nuclear-powered marine propulsion system utilizing a high-temperature, gas-cooled nuclear reactor, close-cycle gas-turbine power plant.
Date: 1960?
Creator: unknown
System: The UNT Digital Library
Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: July-September 1960 (open access)

Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: July-September 1960

Quarterly report discussing activities of the Maritime Gas-Cooled Reactor (MGCR) Program and the progress of the Program in developing a nuclear-powered marine propulsion system utilizing a high-temperature, gas-cooled nuclear reactor, close-cycle gas-turbine power plant.
Date: 1960?
Creator: unknown
System: The UNT Digital Library