A THERMAL ANALYSIS OF ZIRCALOY FUEL-ELEMENT CONTAINERS FOR THE NS SAVANNAH REACTOR

Zircaloy is considered as a substitute for stainless steel in the fuel-element containers for the N.S. Savannah reactor. A thermal analysis was performed to determine the temperature distributions in the Zircaloy fuel-element container walls and spacer bars; these temperature distributions were obtained primarily for use in evaluating thermal stresses. The equations for temperature in the fuel-element coolant, control-rod coolant, and container walls were derived. Gamma-roy energy deposition rates in the Ziracaloy components were calculated. Three-dimensional temperature distributions in the spacer bars were obtained from numerical solutions of the heat-conduction equation. Results are presented in the form of temperature-profile curves for each component and for three reactor operating conditions.(Author)

• Supplemental Notes:
  • This document is available for review at the Department of Commerce Library, Main Commerce Building, Washington, D.C., under reference number ORNL-TM-197.
• Corporate Authors:

  Oak Ridge National Laboratory

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

  UNION CARBIDE CORPORATION

  OAK RIDGE, TN  United States 
• Authors:
  • Anderson, T D
• Publication Date: 1962-9-21

Media Info

• Features: Appendices; Figures; References; Tables;
• Pagination: 42 p.

Subject/Index Terms

• TRT Terms: Fuel elements; Nuclear powered ships; Nuclear reactor coolants; Temperature measurement; Thermal stresses
• Old TRIS Terms: Nuclear reactor fuel elements
• Subject Areas: Marine Transportation; Vehicles and Equipment;

Filing Info

• Accession Number: 00026537
• Record Type: Publication
• Source Agency: Maritime Administration
• Report/Paper Numbers: ORNL-TM-197
• Contract Numbers: W-7405-eng-26
• Files: TRIS, USDOT
• Created Date: Apr 13 1973 12:00AM