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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

Superposition of Forced and Diffusive Flow in a Large-Pore Graphite

Description: Report describing an "investigation of steady-state counter-flow of gases in a large pore graphite" by exposing it to streams of helium and argon.
Date: 1961
Creator: Evans, R. B., III; Truitt, J. & Watson, G. M.
Partner: UNT Libraries Government Documents Department
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Thermonuclear Project Semiannual Progress Report: for Period Ending July 31, 1960

Description: From Introduction: "The present semiannual progress report introduces more active consideration than has been given in the past (by us, at least) to the importance of energy degradation in DCX-like devices. The following pages introduce also a new major apparatus designated as DCX-2. Some of these concepts cannot as yet be released publicly and therefore Chap. 3 of this report, covering the DCX-EP-B design, is being issued separately, with restricted distribution, as ORNL-3044."
Date: January 13, 1961
Partner: UNT Libraries Government Documents Department
open access

Interim Report on Corrosion by Zirconium-Base Fluorides

Description: Report issued by the Oak Ridge National Laboratory discussing studies conducted on corrosion by fluorides. Equipment, procedures, results, and analysis is presented. This report includes tables, illustrations, and photographs.
Date: January 17, 1961
Creator: Adamson, G. M.; Crouse, R. S. & Manly, W. D.
Partner: UNT Libraries Government Documents Department
open access

Final Design Report: DR-1 Gas Loop

Description: Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.
Date: March 1961
Creator: Baars, R. E.
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

Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor

Description: Report describing a 300-Mw(e) Supercritical Pressure Power Reactor's facilities, physics, economics, and problems encountered during its development. Appendix begins on page 103.
Date: June 1961
Creator: Harty, H.; Regimbal, J. J.; Toyoda, K. G. & Widrig, R. D.
Partner: UNT Libraries Government Documents Department
open access

The RBU Reactor-Burnup Code: Formulation and Operation Procedures

Description: Report discussing the computer program RBU, which calculates the neutron, reactivity, and isotopic history of a nuclear reactor in such a way as to facilitate the predictions of fuel costs and reactor performance. This report documents RBU's various calculations and operating procedures.
Date: July 1961
Creator: Triplett, J. R.; Merrill, E. T. & Burr, J. R.
Partner: UNT Libraries Government Documents Department
open access

Numerical Results for EGCR Moderator-Element Stress Problems

Description: From introduction: "A recent report describes the development of a general program for the IBM Type 7090 electronic computer for calculating plane thermal stresses."
Date: July 3, 1961
Creator: Hulbert, Lewis E. & Redmond, Robert F.
Partner: UNT Libraries Government Documents Department
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