SM-2 Final Design Progress Review Report: December 16, 1959 to March 1, 1960 (open access)

SM-2 Final Design Progress Review Report: December 16, 1959 to March 1, 1960

From introduction: "The contract covers final design of the SM-2 Nuclear Power (PWR) Steam Electric Station, described in the preliminary design report, APAE 40, Volumes I and II."
Date: April 6, 1960
Creator: Knighton, G. W.
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
Effect of Superheat and Moisture Separation on the SM-2 Design (open access)

Effect of Superheat and Moisture Separation on the SM-2 Design

From abstract: "The study evaluates the utilization of superheat and moisture separation techniques in the SM-2 design to improve the steam plant reliability and thermal efficiency. Ease of packaging, steam plant transient response, and capital costs are also considered. The reference design used for comparison is the steam cycle employing saturated steam at 600 psia described in APAE No. 40, Volume II."
Date: May 27, 1960
Creator: Phelps, E. F.
System: The UNT Digital Library
Boiling Homogeneous Reactor for Power and U233 Production: Reactor Design and Feasibility Problem (open access)

Boiling Homogeneous Reactor for Power and U233 Production: Reactor Design and Feasibility Problem

Summary report of the study, research, problems and solutions developed in the final ten-weeks period of the school term for a group of men representing various scientific and engineering fields.
Date: August 1954
Creator: Zeitlin, H. R.; Bertini, H. W.; Bourgeois, W. F.; Calvin, J. N.; Engel, J. R.; Farbman, G. H. et al.
System: The UNT Digital Library
An Engineering Test Program to Investigate a Loss of Coolant Accident (open access)

An Engineering Test Program to Investigate a Loss of Coolant Accident

From preface: "The purpose of this report is to present an engineering test program for investigating a loss of coolant accident for a pressurized water-cooled and moderated reactor system."
Date: October 1964
Creator: Wilson, T. R.; Hauge, O. M.; Matheney, G. B. & Homer, G. B.
System: The UNT Digital Library
Engineering Test Reactor : Engineering Design and Safeguards Report (open access)

Engineering Test Reactor : Engineering Design and Safeguards Report

From abstract: "Detail and engineering drawings for the Engineering Test Reactor."
Date: July 1956
Creator: Kaiser Engineers
System: The UNT Digital Library