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
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