Experimental studies of U-Pu-Zr fast reactor fuel pins in EBR-II (Experimental Breeder Reactor)

Conference · Fri Jan 01 00:00:00 EST 1988

OSTI ID:6897067

Pahl, R G; Porter, D L; Lahm, C E; Hofman, G L

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
• Resource Relation: Conference: Symposium on irradiation-enhanced materials science, Chicago, IL, USA, 25 Sep 1988; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
IFR REACTOR
FUEL PINS
DEFORMATION
EBR-2 REACTOR
ECONOMICS
FUEL CANS
FUEL-CLADDING INTERACTIONS
IRRADIATION
PLUTONIUM
REACTOR SAFETY
URANIUM
ZIRCONIUM
ACTINIDES
BREEDER REACTORS
ELEMENTS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
METALS
POWER REACTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SODIUM COOLED REACTORS
TRANSITION ELEMENTS
TRANSURANIUM ELEMENTS
ZERO POWER REACTORS
210500* - Power Reactors
Breeding
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors