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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.
Date:
January 31, 1955
Creator:
unknown
System:
The UNT Digital Library
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.
Date:
1955
Creator:
Thalgott, F. W.
System:
The UNT Digital Library
Transient Temperature Simulation of Reactor Primary Loop
Report issued by the APDA over simulator studies conducted on their Developmental Fast Breeder Reactor. The simulator studies were "designed to predict both the normal and abnormal operating characteristics of the APDA Developmental Fast Breeder Reactor" (p. 1). This report includes tables, and illustrations.
Date:
February 1, 1956
Creator:
Olson, Richard G. & Ritchie, Donald J.
System:
The UNT Digital Library
Equation of State and Heat Content of Uranium
Report issued by the APDA regarting studies conducted on the state of uranium at different temperature and pressure. Calculations are presented for the differing pressures of uranium; it includes tables.
Date:
February 20, 1957
Creator:
Brout, Robert H.
System:
The UNT Digital Library
Report on the Possible Effects on the Surrounding Population of an Assumed Release of Fission Products into the Atmosphere from a 300 Megawatt Nuclear Reactor Located at Lagoona Beach, Michigan
Report issued by the APDA over studies conducted on the release of radioactive particles near Lagoona Beach, Michigan in 1955. "The possible effects on the surrounding population of a release of fission products at the Lagoona Beach site" (p. 1) are discussed. This report includes tables, maps, and illustrations.
Date:
July 1957
Creator:
Gomberg, Henry J.; Bassett, Thomas; Velez, Carlos & Donnell, Alton P.
System:
The UNT Digital Library
Quarterly Report of Research and Development Activities: April - June 1957
Progress report issued by the APDA over research and development activities of the Enrico Fermi Atomic Power Plant. Materials, fuel engineering, and test operations of the plant are presented and discussed.
Date:
1957
Creator:
Atomic Power Development Associates
System:
The UNT Digital Library
Thermal Bowing of Core Subassemblies
Report issued by the APDA over studies conducted on thermal bowing of core sub-assemblies at the Enrico Fermi Atomic Power Plant. As stated in the introduction and summary, "the present report deals with this problem in the design of the Enrico Fermi Reactor and with the method which has been adopted to avoid a positive temperature coefficient of reactivity" (p. 1). This report includes illustrations, and photographs.
Date:
February 20, 1959
Creator:
De Stordeur, Arnold
System:
The UNT Digital Library
Irradiation Testing of Enrico Fermi Prototype Fuel Pins in the CP-5, 1957-1959
Report issued by the APDA over studies conducted on the irradiation of fuel pins in nuclear reactors. As stated in the introduction, "results of these tests have verified predicted high-temperature allowable burn-ups and showed that under certain conditions, excessive swelling could occur at low temperatures" (p. 5). This report includes tables, illustrations, and photographs.
Date:
April 1960
Creator:
Silliman, M. A.; Shoudy, A. A.; Blessing, W. G. & Huebotter, P. R.
System:
The UNT Digital Library
Fuel Enrichment for the Enrico Fermi Reactor
Report issued by the APDA over fuel enrichment processes at the Enrico Fermi Atomic Power Plant. As stated in the introduction, "the results that directly apply to the determination of the enrichment will be given" (p. 6). This report includes tables, and illustrations.
Date:
March 12, 1959
Creator:
Garelis, Edward
System:
The UNT Digital Library
Preliminary Report on Sodium Temperature Coefficients in Large Fast Reactors
Report issued by the APDA over preliminary studies conducted on temperature coefficients in fast breeder reactors. Methods and results of the studies are presented and discussed. This report includes tables, and illustrations.
Date:
1959
Creator:
Nims, J. B. & Zweifel, P. F.
System:
The UNT Digital Library
The Doppler Effect in Fast Neutron Reactors
Report issued by the APDA over studies conducted on the Doppler Effect in fast neutron reactors. Methods and results of the studies are presented and discussed. This report includes tables, and illustrations.
Date:
June 1960
Creator:
Nicholson, Richard Benjamin
System:
The UNT Digital Library
HAFEVER: An Inelastic Scattering Code for the IBM 704 Computer
Report issued by the APDA over HAFEVER, a code developed for the IBM 704 computer. As stated in the introduction, "HAFEVER is an IBM 704 code which calculates the energy exchange inelastic scattering cross section" (p. 3). Descriptions of the code and the theory behind the code are discussed. This report includes tables.
Date:
September 1960
Creator:
Friedman, M. A. & Zweifel, P. F.
System:
The UNT Digital Library
Removal of Sodium from Core Subassemblies with White Oil and Ultrasonics
Report issued by the APDA over methods "for removing sodium from fuel and blanket sub-assemblies that have been irradiated in the reactor of the Enrico Fermi Atomic Power Plant" (p. 3). The cleaning methods are described, as well as experimental studies conducted on them. This report includes illustrations, and photographs.
Date:
1961
Creator:
Kanaan, Z. R. & Nash, C. R.
System:
The UNT Digital Library
Summary of the APDA Fuel Development Programs
Report issued by the APDA over fuel development programs. Designs for fast breeder reactors, safety tests, and methods are presented and discussed. This report includes tables, illustrations, and photographs.
Date:
April 1961
Creator:
Blessing, W. G.; Busch, J. S.; Duffy, J. G.; Hennig, R. J.; Jens, W. H.; Knight, F. W. et al.
System:
The UNT Digital Library
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.
Date:
July 28, 1961
Creator:
Blessing, W. G.; Balsbaugh, R. R.; Bloomfield, D. E.; Busch, J. S.; Hennig, R. J.; Jens, W. H. et al.
System:
The UNT Digital Library
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
Methods for Determining the Energy Release in Hypothetical Reactor Meltdown Accidents
Report and dissertation issued by the APDA over hypothetical reactor meltdown accidents. Methods for the determination of the energy release from reactor meltdowns are presented. This report includes tables, and illustrations.
Date:
December 1962
Creator:
Nicholson, Richard Benjamin
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
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.
Date:
February 23, 1963
Creator:
Doyle, T. A.; Duffy, J. G.; Jens, W. H.; McHugh, W. E.; Page, E. M. & Warberg, H. S.
System:
The UNT Digital Library
Study of Fast Reactor Meltdown Accidents Using Simulant Materials
Report issued by the APDA over studies conducted on reactor meltdown accidents. The studies incorporated the use of simulation materials. Methods and results of the studies are presented and discussed. This report includes tables, illustrations, and photographs.
Date:
August 31, 1963
Creator:
Huebotter, P. R.
System:
The UNT Digital 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.
Date:
November 1, 1963
Creator:
Fischer, E. A.
System:
The UNT Digital Library
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.
Date:
February 17, 1964
Creator:
Ball, G.; DeFelice, J.; Edwards, J. J.; Jens, W. H.; Kovac, L. R.; Poggi, R. et al.
System:
The UNT Digital Library
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.
Date:
March 25, 1964
Creator:
unknown
System:
The UNT Digital Library