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  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: Atomic Power Development Associates Bulletins
 Collection: Technical Report Archive and Image Library
Calculation of the Doppler Coefficient Plutonium-Oxide-Fueled Fast Reactors
Report issued by the APDA over studies conducted on Doppler coefficient fast reactors. Calculations, methods, and results of the studies are presented. This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc38367/
Conceptual Design of an In-Pile Package Loop for Fast Reactor Fuel Testing
Report issued by the APDA over a design study conducted on an "in-pile package loop for use as a reactor fuel test facility" (p. 5). The results are presented and discussed. This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc38360/
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. digital.library.unt.edu/ark:/67531/metadc38361/
Fast Reactor Control and Safety Meeting November 10-11, 1954
Report issued by the APDA over a 2 day reactor safety meeting during November, 1954. A modified transcript of the safety meeting is presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc38347/
Information Report by Atomic Power Development Associates Covering Work from the Period August 1, 1954 to January 31, 1955
Report issued by the APDA over the work conducted between August 1954 and January 1955. Descriptions of the studies, facilities, and equipment used during this time are presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc38346/
Operation of the Sodium Technology Loop for Contamination Meter Evaluations
Report issued by the APDA over studies conducted on the Sodium Technology Loop. Methods, equipment, and results of the studies are presented and discussed. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc38369/
Study of EOCR Modifications for Testing Fast Reactor Fuels
Report issued by the APDA over studies conducted on "methods for increasing the power generation in a fast reactor fuel element test sample" (p. 9). The methods investigated are presented and discussed. This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc38368/
Study of Requirements and Suitability of Available Reactors for Fast Fuel Tests
Report issued by the APDA over studies conducted on the requirements of reactors for fuel testing. As stated in the summary, "the purpose of this study is to determine the requirements for radiation space for fast reactor fuel testing and to determine the capability of existing Commission and private test and power reactors to meet these requirements" (p. 7). This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc38365/