METHODS FOR IMPROVING THE CRITICAL HEAT FLUX FOR BWR'S

This study was made to screen various proposals for increasing the critical heat flux in a nuclear boiling water reactor. The critical heat flux being one of the major limits in the design of a nuclear reactor. The current design operating heat flux is limited below the critical heat flux by a safety factor of 1.5. The ability to decrease the cost of power by increasing the critical heat flux is explored both by hypothesis and experiment. The logic for discarding certain hypothesis and experimenting with film trippers to improve heat transfer in the core is presented. Experimental data for several different designs of film trippers shows great promise in improving rates and reducing nuclear power costs.

• Corporate Authors:

  General Electric

  Marine Turbine & Gear Engineer, 1100 Western Ave
  Lynn, MA  United States  01910
• Authors:
  • Howard, C L
• Publication Date: 1963-3

Media Info

• Pagination: 76 p.

Subject/Index Terms

• TRT Terms: Equipment tests; Fuel elements; Nuclear reactors; Safety
• Old TRIS Terms: Nuclear reactor fuel elements; Nuclear reactor safety; Nuclear reactor testing
• Subject Areas: Marine Transportation; Safety and Human Factors;

Filing Info

• Accession Number: 00026702
• Record Type: Publication
• Source Agency: National Technical Information Service
• Contract Numbers: AT(04-3)-189
• Files: TRIS
• Created Date: Jun 1 1973 12:00AM