GENERAL DESCRIPTION AND OPERATING INFORMATION FOR EXPERIMENTS 5 AND 7 IN THE ORR PRESSURIZED-WATER LOOP

Analysis is presented of nonsintered fuel rods irradiated in the A-1 and A-2 pressurized-water loop concurrently. Fuel specimens, assembled in clusters of three, were fabricated primarily by fused-and-ground uranium dioxide; the cold swaged method was also utilized. Predicted loop performance characteristics (including temperature, enthalpy, density, velocity, and friction factor) for both experiments are presented for nominal and scram conditions.

• Supplemental Notes:
  • This document is available for review at the Department of Commerce Library, Main Commerce Building, Washington, D.C., under reference number ORNL-CF-61-11-58.
• Corporate Authors:

  Oak Ridge National Laboratory

  P. O. Box 2008
  Oak Ridge, TN  United States  37831

  Union Carbide Nuclear Company

  ,    
• Authors:
  • Haynes, V O
• Publication Date: 1961-11-1

Media Info

• Features: Figures; References; Tables;
• Pagination: 11 p.

Subject/Index Terms

• TRT Terms: Fuel elements; Fuel systems; Nuclear reactors; Operations
• Old TRIS Terms: Nuclear reactor fuel elements; Nuclear reactor operation
• Subject Areas: Administration and Management; Marine Transportation; Vehicles and Equipment;

Filing Info

• Accession Number: 00026420
• Record Type: Publication
• Source Agency: Maritime Administration
• Contract Numbers: W-7405-eng-26
• Files: TRIS, USDOT
• Created Date: Apr 13 1973 12:00AM