Liquid Metal Fast Breeder Reactor Design Study (open access)

Liquid Metal Fast Breeder Reactor Design Study

From introduction: "The primary objective of the present study was to develop a conceptual design of a large sodium cooled fast breeder reactor of a nominal electrical rating of 1000 Mw operating on the uranium-plutonium cycle."
Date: January 1964
Creator: unknown
System: The UNT Digital Library
A Single Stage Axial Compressor Blade Test Facility (open access)

A Single Stage Axial Compressor Blade Test Facility

Abstract: This report gives a general description of the single stage axial compressor blade test facility located at the Oak Ridge Gaseous Diffusion Plant, Oak Ridge, Tennessee.
Date: January 13, 1964
Creator: Fee, G. G.
System: The UNT Digital Library
Inpile Experiments on Retention of Fission Products in 500°F Sodium (open access)

Inpile Experiments on Retention of Fission Products in 500°F Sodium

Abstract: The results of three separate inpile capsule experiments are presented.
Date: January 30, 1964
Creator: Kunkel, W. P.; Elliot, D. M. & Gibson, A. S.
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: September 1, 1963 - December 1, 1963 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: September 1, 1963 - December 1, 1963

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: January 1, 1964
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Collins, William R., Jr.
System: The UNT Digital Library
Hanford Radiological Sciences Research and Development Annual Report for 1963 (open access)

Hanford Radiological Sciences Research and Development Annual Report for 1963

Report regarding ongoing research and development undertaken at Hanfdord Laboratories' physics and instruments laboratory and chemical laboratory.
Date: January 1964
Creator: Gamertsfelder, C. C. & Green, J. K.
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
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
Gas-Cooled Reactor Project Semiannual Progress Report: September 1963 (open access)

Gas-Cooled Reactor Project Semiannual Progress Report: September 1963

Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Date: January 29, 1964
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Hanford Graphite Superheat Reactor (HGSR) Design Study and Evaluation (open access)

Hanford Graphite Superheat Reactor (HGSR) Design Study and Evaluation

Report containing the results of a preliminary study of a design concept for a graphite-moderated pressure tube reactor. Topics include reactor design, operating procedures, subsystems, hazards analysis, and economic potential. Appendices begin on page 174.
Date: January 1964
Creator: Hanford Atomic Products Operation. N-Reactor Project Section.
System: The UNT Digital Library
Advanced Test Reactor Turbo Report (open access)

Advanced Test Reactor Turbo Report

From abstract: "The time-dependent behavior of the Advanced Test Reactor was calculated by the Babcock & Wilcox Company on the Philco 2000 computer, using the Turbo depletion program."
Date: January 1964
Creator: Turner, Robert A.
System: The UNT Digital Library
Advanced Test Reactor Burnout Heat Transfer Tests (open access)

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