Loop irradiation studies on urania fuel rods are reported for the nuclear merchant ship reactor. Two series of loop specimens containing UO2 fuel pellets, clad with Type 304 stainless steel, were tested in a high-pressure, high-temperature loop to determine their behavior under irradiation. There were six short fuel rods in the short-term-irradiation series with an enrichment of 7.48%. The specimens were irradiated to burnups of 0.09 to 0.11 a/o of uranium. The only significant change in the rods was an oxide deposit on the cladding after irradiation. The dimensions, densities, and microstructures of the cladding and fuel did not exhibit any observable change after the irradiation test. In the long-term irradiation one long fuel rod was irradiated for seven cycles, resulting in an estimated burnup of 0.5 a/o of uranium. During irradiation a smooth oxide coating was deposited on the stainless steel cladding, but no changes in dimensions or bowing took place.

  • Supplemental Notes:
    • This document is available for review at the Department of Commerce Library, Main Commerce Building, Washington, D.C., under reference number BMI-B&W-661 (with Add.).
  • Corporate Authors:

    Battelle Memorial Institute

    505 King Avenue
    Columbus, OH  United States  43201

    Babcock and Wilcox Company

    Atomic Energy Division
    Lynchburg, VA  United States  24504
  • Authors:
    • Kangilaski, M
    • Franklin, C K
    • Hare, A W
    • Dickerson, R F
  • Publication Date: 1962-3-13

Media Info

  • Features: Appendices; Figures; References; Tables;
  • Pagination: 57 p.

Subject/Index Terms

Filing Info

  • Accession Number: 00026368
  • Record Type: Publication
  • Source Agency: Maritime Administration
  • Report/Paper Numbers: BMI-B&W-661
  • Contract Numbers: AT(30-3)-274
  • Files: TRIS, USDOT
  • Created Date: Feb 6 1973 12:00AM