Irradiation Testing of Enrico Fermi Prototype Fuel Pins in the CP-5, 1957-1959 (open access)

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
The Doppler Effect in Fast Neutron Reactors (open access)

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 (open access)

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 (open access)

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 (open access)

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 (open access)

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 (open access)

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 (open access)

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 (open access)

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 (open access)

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 (open access)

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 (open access)

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 (open access)

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 (open access)

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 (open access)

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
Fast Reactor Core Design Parameter Study (open access)

Fast Reactor Core Design Parameter Study

Report describing parametric studies of eleven fast reactor fuel systems undertaken to determine the design and economic factors for producing electricity. The methods used for making the parametric studies are described, as well as the results of these studies. Appendices begin on page 103.
Date: March 1960
Creator: Atomic Power Development Associates
System: The UNT Digital Library
Enrico Fermi Atomic Power Plant (open access)

Enrico Fermi Atomic Power Plant

Report describing the Enrico Fermi Atomic Power Plant, its fast breeder reactor, and heat transport systems.
Date: March 1960
Creator: Atomic Power Development Associates
System: The UNT Digital Library
Fast Reactor Fuel Cycle Costs and Temperature Coefficients of Reactivity for PuO2-SS and PuO2-UO2 (open access)

Fast Reactor Fuel Cycle Costs and Temperature Coefficients of Reactivity for PuO2-SS and PuO2-UO2

Report comparing the fuel cycle costs and temperature coefficients of reactivity for PuO2-UO2 fuel in multiple megawatt reactors.
Date: April 25, 1963
Creator: Edwards, J. J.; Fischer, E. A.; Jens, W. H.; Nims, J. B.; Palmer, R. G.; Shoudy, A. A. et al.
System: The UNT Digital Library
Design and Economic Evaluation of Fixed Blankets for Fast Reactors (open access)

Design and Economic Evaluation of Fixed Blankets for Fast Reactors

Report evaluating the design characteristics and limitations of fixed blankets for breeder reactors. This also includes economic considerations for each tested blanket.
Date: August 30, 1963
Creator: Klickman, A. E.; Ball, G. L.; Edwards, J. J.; Jens, W. H.; Segal, B. M.; Stanford, R. E. L. et al.
System: The UNT Digital Library
Design and Economic Evaluation of Mobile Blankets for Fast Reactors (open access)

Design and Economic Evaluation of Mobile Blankets for Fast Reactors

Report evaluating the design characteristics and limitations of mobile blankets for breeder reactors. This also includes economic considerations for each tested blanket. Appendices begin on page 40.
Date: March 10, 1964
Creator: Klickman, A. E.; Ball, G. L.; Edwards, J. J.; Jens, W. H.; Segal, B. M.; Amorosi, A. et al.
System: The UNT Digital Library