Metallurgical Transactions A

, Volume 21, Issue 7, pp 1863–1870 | Cite as

Experimental studies of U-Pu-Zr fast reactor fuel pins in the experimental breeder reactor-ll

  • R. G. Pahl
  • D. L. Porter
  • C. E. Lahm
  • G. L. Hofman
Irradiation-enhanced materials science and engineering (Part III) (Part I appeared in volume 20A, December 1989) (Part II appeared in volume 21 A, May 1990)


Argonne National Laboratory’s Integral Fast Reactor (IFR) concept has been under demonstration in the Experimental Breeder Reactor II (EBR-II) since February 1985. Irradiation tests of U-Zr and U-Pu-Zr fuel pins to >15 at. pct burnup have demonstrated their viability as driver fuel prototypes in innovative design liquid metal reactors. A number of technically challenging irradiation effects have been observed and are now under study. Microstructural changes in the fuel are dominated early in exposure by grain boundary cavitation and fission gas bubble growth, producing large amounts of swelling. Irradiation creep and swelling of the austenitic (D9) and martensitic (HT-9) candidate cladding alloys have been measured and correlate well with property modeling efforts. Chemical interaction between the fuel and cladding alloys has been characterized to assess the magnitude of cladding wastage during steady-state irradiation. Significant interdiffusion of the uranium and zirconium occurs producing metallurgically distinct zones in the fuel.


Metallurgical Transaction Argonne National Laboratory Metallic Fuel Fuel Alloy Fuel Slug 
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Copyright information

© The Metallurgical of Society of AIME 1990

Authors and Affiliations

  • R. G. Pahl
    • 1
  • D. L. Porter
    • 1
  • C. E. Lahm
    • 1
  • G. L. Hofman
    • 2
  1. 1.Experimental Breeder Reactor-ll DivisionArgonne National LaboratoryIdaho Falls
  2. 2.Argonne National LaboratoryArgonne

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