PHOENIX FUEL EVALUATION IN A MARITIME REACTOR DESIGN

The Consolidated Nuclear Steam Generator - II reactor concept was used as a reference design to compare fuel cycle costs for Pu fueled cores with a high 240Pu content ( Phoenix fuel ) to costs for an enriched U base case core. The Phoenix fuel was found to be competitive with the slightly enriched U reference fuel. Results are presented in graphical and tabular form, and the results and calculational methods are discussed. ( H.D.R. )

• Corporate Authors:

  Pacific Northwest National Laboratory

  3180 George Washington Way
  Richland, WA  United States  99354
• Authors:
  • Wise, K R
  • Jenquin, U P
• Publication Date: 1968-10

Media Info

• Pagination: 38 p.

Subject/Index Terms

• TRT Terms: Fuel elements; Nuclear fuels; Nuclear power generation; Nuclear reactor cores; Nuclear reactors; Radioactive materials; Reactor fuel cycle
• Old TRIS Terms: Consolidated nuclear steam generators; Nuclear fuel cycles; Nuclear reactor fuel elements; Nuclear reactor materials
• Subject Areas: Energy; Marine Transportation;

Filing Info

• Accession Number: 00001604
• Record Type: Publication
• Source Agency: National Technical Information Service
• Contract Numbers: AT451-1830
• Files: TRIS
• Created Date: Oct 30 1973 12:00AM