Experimental studies of U-Pu-Zr fast reactor fuel pins in EBR-II (Experimental Breeder Reactor)
The Integral Fast Reactor (IFR) is a generic reactor concept under development by Argonne National Laboratory. Much of the technology for the IFR is being demonstrated at the Experimental Breeder Reactor II (EBR-II) on the Department of Energy site near Idaho Falls, Idaho. The IFR concept relies on four technical features to achieve breakthroughs in nuclear power economics and safety: (1) a pool-type reactor configuration, (2) liquid sodium cooling, (3) metallic fuel, and (4) an integral fuel cycle with on-site reprocessing. The purpose of this paper will be to summarize our latest results of irradiation testing uranium-plutonium-zirconium (U-Pu-Zr) fuel in the EBR-II. 10 refs., 13 figs., 2 tabs.
- Research Organization:
- Argonne National Lab., Idaho Falls, ID (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6897067
- Report Number(s):
- CONF-8809202-2; ON: DE89003628
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210500* -- Power Reactors
Breeding
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDES
BREEDER REACTORS
DEFORMATION
EBR-2 REACTOR
ECONOMICS
ELEMENTS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL CANS
FUEL ELEMENTS
FUEL PINS
FUEL-CLADDING INTERACTIONS
IFR REACTOR
IRRADIATION
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
METALS
PLUTONIUM
POWER REACTORS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SODIUM COOLED REACTORS
TRANSITION ELEMENTS
TRANSURANIUM ELEMENTS
URANIUM
ZERO POWER REACTORS
ZIRCONIUM