THE FABRICATION AND IRRADIATION TESTING OF DISPERSION-TYPE BEO-UO SUB 2 CERAMIC FUEL MATERIALS

Considerations affecting the design of dispersion-type ceramic fuel materials are discussed. The results of measurements made to study the effect of fuel loading on the properties of the fuel bodies and the results of irradiation tests of fuel pellets composed of 20 vol % UO sub 2 dispersed in BeO are presented. Experience in the fabrication of dispersion-type BeO-UO sub 2 ceramic fuel materials is described. From the results obtained, it is believed that BeO-UO sub 2 fuel materials of the type studied will exhibit satisfactory performance in the Experimental Beryllium Oxide Reactor.(Author)

• Corporate Authors:

  General Dynamics

  Quincy, MA  United States  02169
• Authors:
  • JOHNSON, D E
  • Lofftus, F H
• Publication Date: 1962-10-10

Media Info

• Pagination: 26 p.

Subject/Index Terms

• TRT Terms: Equipment tests; Fuel elements; Fuel processing; Nuclear fuels; Nuclear reactors
• Old TRIS Terms: Nuclear fuel processing; Nuclear reactor fuel elements; Nuclear reactor testing
• Subject Areas: Energy; Marine Transportation;

Filing Info

• Accession Number: 00026568
• Record Type: Publication
• Source Agency: National Technical Information Service
• Contract Numbers: AT(04-3)-187
• Files: TRIS
• Created Date: May 4 1973 12:00AM