Conceptual design of an in-pile package loop for sodium-cooled thermal reactor fuel testing

Conceptual design of an in-pile package loop for sodium-cooled thermal reactor fuel testing

Date: September 15, 1961
Creator: Blessing, W. G.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Calculation of the Doppler Coefficient Plutonium-Oxide-Fueled Fast Reactors

Calculation of the Doppler Coefficient Plutonium-Oxide-Fueled Fast Reactors

Date: November 1, 1963
Creator: Fischer, E. A.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Conceptual Design of an In-Pile Package Loop for Fast Reactor Fuel Testing

Conceptual Design of an In-Pile Package Loop for Fast Reactor Fuel Testing

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.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Study of EOCR Modifications for Testing Fast Reactor Fuels

Study of EOCR Modifications for Testing Fast Reactor Fuels

Date: February 17, 1964
Creator: Ball, G.; DeFelice, J.; Edwards, J. J.; Jens, W. H.; Kovac, L. R.; Poggi, R. et al.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Two-Facility Approach to Investigations of Fast Reactor Meltdowns

Two-Facility Approach to Investigations of Fast Reactor Meltdowns

Date: January 15, 1963
Creator: Doyle, T. A.; Page, E. M.; Nicholson, R. B.; Hagstrom, J. T. & Nims, J. B.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Operation of the Sodium Technology Loop for Contamination Meter Evaluations

Operation of the Sodium Technology Loop for Contamination Meter Evaluations

Date: March 25, 1964
Creator: unknown
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Study of Requirements and Suitability of Available Reactors for Fast Fuel Tests

Study of Requirements and Suitability of Available Reactors for Fast Fuel Tests

Date: February 23, 1963
Creator: Doyle, T. A.; Duffy, J. G.; Jens, W. H.; McHugh, W. E.; Page, E. M. & Warberg, H. S.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Evaluation of the Blake Sodium Resistivity Meter

Evaluation of the Blake Sodium Resistivity Meter

Date: October 15, 1962
Creator: Atomic Power Development Associates
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Study of Fast Reactor Meltdown Accidents Using Simulant Materials

Study of Fast Reactor Meltdown Accidents Using Simulant Materials

Date: August 31, 1963
Creator: Huebotter, P. R.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Methods for Determining the Energy Release in Hypothetical Reactor Meltdown Accidents

Methods for Determining the Energy Release in Hypothetical Reactor Meltdown Accidents

Date: December 1962
Creator: Nicholson, Richard Benjamin
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Thermal Bowing of Core Subassemblies

Thermal Bowing of Core Subassemblies

Date: February 20, 1959
Creator: De Stordeur, Arnold
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Quarterly Report of Research and Development Activities: April - June 1957

Quarterly Report of Research and Development Activities: April - June 1957

Date: 1957
Creator: Atomic Power Development Associates
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
HAFEVER: An Inelastic Scattering Code for the IBM 704 Computer

HAFEVER: An Inelastic Scattering Code for the IBM 704 Computer

Date: September 1960
Creator: Friedman, M. A. & Zweifel, P. F.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Removal of Sodium from Core Subassemblies with White Oil and Ultrasonics

Removal of Sodium from Core Subassemblies with White Oil and Ultrasonics

Date: 1961
Creator: Kanaan, Z. R. & Nash, C. R.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Fuel Enrichment for the Enrico Fermi Reactor

Fuel Enrichment for the Enrico Fermi Reactor

Date: March 12, 1959
Creator: Garelis, Edward
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Summary of the APDA Fuel Development Programs

Summary of the APDA Fuel Development Programs

Date: April 1961
Creator: Blessing, W. G.; Busch, J. S.; Duffy, J. G.; Hennig, R. J.; Jens, W. H.; Knight, F. W. et al.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
The Doppler Effect in Fast Neutron Reactors

The Doppler Effect in Fast Neutron Reactors

Date: June 1960
Creator: Nicholson, Richard Benjamin
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Irradiation Testing of Enrico Fermi Prototype Fuel Pins in the CP-5, 1957-1959

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

Date: April 1960
Creator: Silliman, M. A.; Shoudy, A. A.; Blessing, W. G. & Huebotter, P. R.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Fast Reactor Control and Safety Meeting November 10-11, 1954

Fast Reactor Control and Safety Meeting November 10-11, 1954

Date: 1955
Creator: Thalgott, F. W.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Transient Temperature Simulation of Reactor Primary Loop

Transient Temperature Simulation of Reactor Primary Loop

Date: February 1, 1956
Creator: Olson, Richard G. & Ritchie, Donald J.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Equation of State and Heat Content of Uranium

Equation of State and Heat Content of Uranium

Date: February 20, 1957
Creator: Brout, Robert H.
Description: Report issued by the APDA over studies conducted on the state of uranium at different temperature and pressure. Calculations are presented for the differing pressures of uranium. This report includes tables.
Contributing Partner: UNT Libraries Government Documents Department
Information Report by Atomic Power Development Associates Covering Work from the Period August 1, 1954 to January 31, 1955

Information Report by Atomic Power Development Associates Covering Work from the Period August 1, 1954 to January 31, 1955

Date: January 31, 1955
Creator: unknown
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Fast Reactor Fuel Cycle Costs and Temperature Coefficients of Reactivity for PuO2-SS and PuO2-UO2

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

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.
Description: Report comparing the fuel cycle costs and temperature coefficients of reactivity for PuO2-UO2 fuel in multiple megawatt reactors.
Contributing Partner: UNT Libraries Government Documents Department
Preliminary Report on Sodium Temperature Coefficients in Large Fast Reactors

Preliminary Report on Sodium Temperature Coefficients in Large Fast Reactors

Date: 1959
Creator: Nims, J. B. & Zweifel, P. F.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department