Design Study: Sodium Modular Reactor (open access)

Design Study: Sodium Modular Reactor

This study was undertaken for the USAEC under Contract AT(04-3)-189, Project Agreement No. 6, to investigate desirable features of a sodium cooled, graphite moderated uranium fueled power reactor using the modular concept, and, based on this investigation, evaluate the economic potential of this reactor type.
Date: January 15, 1960
Creator: General Electric Company
System: The UNT Digital Library
Steam-Cooled Power Reactor Evaluation: Study of 300 Mw(e) Once-Through Superheater Reactor (open access)

Steam-Cooled Power Reactor Evaluation: Study of 300 Mw(e) Once-Through Superheater Reactor

From introduction: "This report presents a conceptual design study of the once-through superheat reactor design based on experimental heat transfer results obtained during the fall of 1960 on Task F-2 of the AEC sponsored Nuclear Superheat Project."
Date: January 1961
Creator: U.S. Atomic Energy Commission
System: The UNT Digital Library
Liquid Metal Fast Breeder Reactor Design Study: Volume 1 (open access)

Liquid Metal Fast Breeder Reactor Design Study: Volume 1

From abstract: "A detailed description of a reference 1000-MWe fast breeder reactor plant is presented, together with design specifications and the experimental bases for the design."
Date: January 1964
Creator: General Electric Company
System: The UNT Digital Library
High Power Density Development Project: Interim Report, 300 MWe HPD Conceptual Design Study (open access)

High Power Density Development Project: Interim Report, 300 MWe HPD Conceptual Design Study

From introduction: "Preliminary design and analysis of the 300 MWe core."
Date: January 5, 1962
Creator: Grayhek, V. G.
System: The UNT Digital Library
Liquid Metal Fast Breeder Reactor Design Study: Volume 2 (open access)

Liquid Metal Fast Breeder Reactor Design Study: Volume 2

From introduction: "Documentation of the various considerations and design techniques involved in the design of the reference 1000-MWe fast oxide breeder reactor."
Date: January 1964
Creator: General Electric Company
System: The UNT Digital Library
A Survey of Water Reactor Primary System Conditions Pertinent to the Study of Pipe Rupture (open access)

A Survey of Water Reactor Primary System Conditions Pertinent to the Study of Pipe Rupture

"Designers, builders and operators of water cooled reactor systems have been queried regarding the range of parameters which should be investigated in a study of piping rupture."
Date: January 1964
Creator: U.S. Atomic Energy Commission
System: The UNT Digital Library