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Corn Pone: A Multigroup, Multiregion Reactor Code

Description: Report covering the development of a set of difference equations for machine solution. In addition, this report serves as user's manual for Corn Pone, which is a code for the Oracle, the Oak Ridge National Laboratory computer.
Date: 1961?
Creator: Kinney, W. E. & Coveyou, R. R.
Partner: UNT Libraries Government Documents Department
open access

Experimental Stress Analysis of EGCR Pressure Vessel

Description: Report regarding the structural evaluations made of the upper head of the Experimental Gas Cooled Reactor (EGCR). This report includes descriptions of the model, experimental procedures, and analyses of the results. Appendix begins on page 139.
Date: 1961
Creator: Greenstreet, B. L.; Holland, R. W.; Maxwell, R. L.; Witt, F. J.; Shobe, L. R. & LaVerne, M. E.
Partner: UNT Libraries Government Documents Department
open access

Health and Safety Laboratory Fallout Program Quarterly Summary Report: September 1, 1960 - December 1, 1960

Description: Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: January 9, 1961
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1

Description: Report discussing the evaluation of the "behavior of austenitic and ferritic stainless steels, iron-chromium-aluminum base alloys and nickel-base superalloys, in medium and high temperature simulated reactor environments" (p. 2).
Date: February 1961
Creator: Pessl, H. J.
Partner: UNT Libraries Government Documents Department
open access

Supplemental Report on New Production Reactor Power Plant Economic Feasibility Study: Volume 1-S

Description: From purpose and scope of study: This report contains a primary study based on estimated loads and resources deemed most likely to occur and a secondary study based on the sale by the summer of 1961 of an additional 400 MW of power to industries resulting in an equal increase in loads.
Date: February 1961
Partner: UNT Libraries Government Documents Department
open access

A Report on Some Attempts to Cast Centrifugally Fuel Elements of Small Diameter

Description: Report issued by the Argonne national Laboratory discussing centrifugal casting of thin uranium plates. The applicability of the centrifugal casting technique to the production of multiple castings of fuel pins of small diameter and of thin fuel plates was investigated. This report includes tables, illustrations, and photographs.
Date: March 1961
Creator: Yaggee, F. L.
Partner: UNT Libraries Government Documents Department
open access

The Cold Pressing of Sinterable UO₂

Description: The intent of this work was to explore more fully the pressing of sinterable UO2 powders into cylindrical compacts in the hope that a more precise prediction of green density in terms of powder properties, pressure, and geometry could be evolved.
Date: March 27, 1961
Creator: Levey, R. P., Jr.
Partner: UNT Libraries Government Documents Department
open access

Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1960 - March 1, 1961

Description: Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: April 1, 1961
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
Partner: UNT Libraries Government Documents Department
open access

Fabrication Development of UO2-Stainless Steel Composite Fuel Plates for core B of the Enrico Fermi Fast Breeder Reactor

Description: Experimental work concerned with the development of an inexpensive composite fuel plate with a high burnup potential for application in a 500°C sodium environment as Core B of the Enrico Fermi Fast Breeder Reactor.
Date: April 18, 1961
Creator: Cherubini, J. H.; Beaver, R. J. & Leitten, C. F., Jr.
Partner: UNT Libraries Government Documents Department
open access

Uranium-Bismuth In-Pile Corrosion Test Loop: Radiation Loop No. 1

Description: Report issued by the Brookhaven National Laboratory discussing uranium-bismuth corrosion test loops. Design, construction, and operation of the test loops are presented. This report includes tables, illustrations, and photographs.
Date: May 1961
Creator: Waide, C. H.; Kukacka, L. E.; Meyer, R. A.; Milau, J.; Klein, J. H.; Chow, J. G. Y. et al.
Partner: UNT Libraries Government Documents Department
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