EXPERIMENTAL EVALUATION OF HELICAL CONSOLIDATED NUCLEAR STEAM GENERATOR (CNSG) TUBES AND SUPPORTS

Results derived from the experimental phase of the helical steam generator tube support evaluation program are presented. The objective was to evaluate prototype steam generator tubes and proposed supports based on tube vibration criteria, and to verify results derived earlier during the analytical phase. In-air and flow-induced vibration tests were performed. Tube vibration characteristics were obtained as a function of support spacing and degree of fixty. Response of helical tubes under simulated CNSG flow conditions was also studied. Results associating tube natural frequency, displacement, support fixity, and tube span length were significant. Acceptable flow-induced tube vibration characteristics were also observed. Experimental results also agreed favorably with corresponding analytical predictions. An adequate tube support design and spacing arrangement was identified. However, additional testing is required to predict life expectancy. Finally, experimental results demonstrate that analytical techniques developed to investigate response of helical tubes under various support and excitation conditions are valid.

• Supplemental Notes:
  • Restricted distribution: Requests for copy to Office of Advanced Ship Development, Maritime Administration.
• Corporate Authors:

  Babcock and Wilcox Company

  Alliance Research Center
  Alliance, OH  United States  44601
• Authors:
  • Glosser, R P
• Publication Date: 1975-11

Subject/Index Terms

• TRT Terms: Flow; Nuclear power generation; Vibration
• Old TRIS Terms: Boiler tube supports; Boiler tube vibration; Consolidated nuclear steam generators; Flow induced vibration
• Subject Areas: Marine Transportation; Vehicles and Equipment;

Filing Info

• Accession Number: 00147558
• Record Type: Publication
• Source Agency: Maritime Administration
• Report/Paper Numbers: MA-RD-920-76019
• Contract Numbers: 1-35555
• Files: TRIS, USDOT
• Created Date: Feb 16 1977 12:00AM