Search Results

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

Engineering Test Reactor Critical Facility Control System Manual

Description: This report consists of the description, drawings, connections, and schematics of the various control elements that make up the control system of the Engineering Test Reactor Critical Facility (ETRC).
Date: June 23, 1961
Creator: Meichle, F. A.
Partner: UNT Libraries Government Documents Department

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

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

Chemical Technology Division Annual Progress Report, May 31, 1961

Description: Report documenting the ongoing research and developments of the Chemical Technology Division of the Oak Ridge National Laboratory.
Date: September 21, 1961
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
Partner: UNT Libraries Government Documents Department

Health Physics Division Annual Progress Report, July 31, 1961

Description: Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.
Date: October 31, 1961
Creator: Oak Ridge National Laboratory. Health Physics Division.
Partner: UNT Libraries Government Documents Department

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

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

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

The Thermal Hydraulics Laboratory at Hanford

Description: Report describing the experimental facilities of Hanford's Thermal Hydraulics Laboratory, its equipment, personnel, operating schedules, and safety procedures. Appendix begins on page 49.
Date: November 1961
Creator: Batch, J. M.; Toyoda, K. G. & Hanthorn, H. E.
Partner: UNT Libraries Government Documents Department

Steam Cooled Power Reactor Evaluation - Beloyarsk (Ural) Reactor

Description: Report evaluating "the effects of nuclear steam superheating, as utilized in the Russian design, on the economics of electric power production, assuming the use of such a design in the United States" (p. 1). This report includes a description of the Beloyarsk Station and modifications made to the Russian designs for use in the United States.
Date: April 1961
Creator: Hanford Works
Partner: UNT Libraries Government Documents Department