IRRADATION AND POST IRRADATION EXAMINATION OF NS SAVANNAH TEST FUEL ELEMENT S1-A

Modified core I fuel element following irradiation in the VBWR and post-irradiation examination, provided data on the irradiation performance of this element at maximum heat fluxes comparable to those expected in the N.S Savannah core I reactor. The modified element was of brazed ferrule design and consisted of 16 fuel rods in a square lattice. Post radiation examination revealed no evidence damage, corrosion, or significant dimensional changes. No evidence of fuel melting was observed and extensive pellet fragmentation was limited to peak burnup regions. Metallographic examinaton revealed no significant ferrule braze or end cap weld damage. An apparent fuel density increase of 4% was observed.

  • Supplemental Notes:
    • This document is available for review at the Department of Commerce Library, Main Commerce Building, Washington, D.C., under reference number GEAP-3342.
  • Corporate Authors:

    General Electric

    Marine Turbine & Gear Engineer, 1100 Western Ave
    Lynn, MA  USA  01910
  • Authors:
    • Zimmerman, D L
  • Publication Date: 1960-1-28

Media Info

  • Features: Appendices; Figures; References; Tables;
  • Pagination: 73 p.

Subject/Index Terms

Filing Info

  • Accession Number: 00026300
  • Record Type: Publication
  • Source Agency: Maritime Administration
  • Report/Paper Numbers: GEAP-3342
  • Contract Numbers: AT(04-3)-189
  • Files: TRIS, USDOT
  • Created Date: May 4 1973 12:00AM