NS SAVANNAH PRIMARY GATE VALVE STRESS REPORT. INVESTIGATION OF LOW CYCLE FATIGUE RESULTING FROM VARIOUS TRANSIENTS DURING REACTOR OPERATION

This report on an evaluation of the possible occurrence of craze cracks on the inner surfaces of the primary gate valve in the N.S. Savannah due to previous thermal cycles, and tries to determine if future transients could propagate these cracks if they were initially present. It concludes that the safety of the primary piping system has not been impaired by thermal transients which have occurred during service, that cold water make up transients may have initiated surface crazing over a small area of the inner surface of the valve, and that future transients will not be a source of concern since the most severe of these has been eliminated by introducing the make up water at a more favorable location.

• Supplemental Notes:
  • This document is available for review at the Department of Commerce Library, Main Commerce Building, Washington, D.C., under reference number BAW-1290, Ca-7.
• Corporate Authors:

  Babcock and Wilcox Company

  Atomic Energy Division
  Lynchburg, VA  United States  24504
• Authors:
  • Ross, H D
• Publication Date: 1963-11

Media Info

• Features: Appendices; Figures; References; Tables;
• Pagination: 24 p.

Subject/Index Terms

• TRT Terms: Cracking; Fatigue cracking; Nuclear powered ships; Nuclear reactors; Operations; Structural analysis
• Old TRIS Terms: Nuclear reactor operation
• Subject Areas: Administration and Management; Marine Transportation; Vehicles and Equipment;

Filing Info

• Accession Number: 00026673
• Record Type: Publication
• Source Agency: Maritime Administration
• Report/Paper Numbers: BAW-1290, Ca-7
• Contract Numbers: AT(30-1)-3215
• Files: TRIS, USDOT
• Created Date: May 11 1973 12:00AM