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  USA  99354
  • Authors:
    • Wise, K R
    • Jenquin, U P
  • Publication Date: 1968-10

Media Info

  • Pagination: 38 p.

Subject/Index Terms

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