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Conceptual design of an in-pile package loop for sodium-cooled thermal reactor fuel testing
Report issued by the APDA over a design study "of a facility for testing sodium-cooled thermal reactor fuel assemblies in the Advanced Test Reactor" (p. 5). The results are presented and discussed. This report includes tables, and illustrations.
Date:
September 15, 1961
Creator:
Blessing, W. G.
System:
The UNT Digital Library
Evaluation of the Blake Sodium Resistivity Meter
Report issued by the APDA over an evaluation of the toroid sodium resistivity meter. Studies were conducted on carbon and oxygen contamination. As stated in the introduction, "the meter was also subjected to extensive testing in which variations in temperature, flow rate, and supply voltage were made in order to determine signal stability and effective range" (p. 5). This report includes tables, illustrations, and photographs.
Date:
October 15, 1962
Creator:
Atomic Power Development Associates
System:
The UNT Digital Library
Two-Facility Approach to Investigations of Fast Reactor Meltdowns
Report issued by the APDA over studies conducted on hypothetical fast reactor meltdown accidents. As stated in the summary, "the purpose of this study is to investigate the technical feasibility of conducting fast reactor meltdown experiments to determine a more realistic maximum accident and to provide a better evaluation of fast reactor safety" (p. 7). This report includes tables, and illustrations.
Date:
January 15, 1963
Creator:
Doyle, T. A.; Page, E. M.; Nicholson, R. B.; Hagstrom, J. T. & Nims, J. B.
System:
The UNT Digital Library