Characteristics of uo2-zr fuel rods irradiated in the br3 reactor
Characteristics of uo2-zr fuel rods irradiated in the br3 reactor

Author: J. P. Adams

Publisher:

Published: 1984

Total Pages: 0

ISBN-13:

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This report summarizes the characterization studies performed on 100 uranium fuel rods irradiated in the br-3 reactor under the direction of belgonucleaire, s.a. in mol, belgium. the irradiation history and fuel content, as reported by belgonucleaire, are included for all fuel rods as are the results of nondestructive and destructive examinations performed by eg&g idaho, inc., and argonne-west personnel on a selected sample of the fuel rods. these fuel rods are scheduled for use in experiments at the power burst facility (in the severe fuel damage experiment series) and in the transient reactor test facility (treat) (in the source term experiment program) at the idaho national engineering laboratory.

Examination of Uranium-2 W/o Zirconium Experimental Fuel Slugs Irradiated in EBR-I
Examination of Uranium-2 W/o Zirconium Experimental Fuel Slugs Irradiated in EBR-I

Author: W. F. Murphy

Publisher:

Published: 1962

Total Pages: 58

ISBN-13:

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Six groups of U-2 wt% Zr fuel slugs were irradiated in the first core of the EBR-I to burnups of 0.080 to 0.189 at.% at calculated temperatures of 307 to 353 deg C. Two groups of cast specimens were found to be more dimensionally stable than four groups of wrought slugs. Of the wrought slugs, the as quenched group showed less tendency to grow than the three groups which had some annealing after quenching. Specimens at burnups of about 0.189 at.% and at 383 deg C showed the onset of swelling as indicated by density measurements. The hardness of these specimens seemed but little affected by radiation, but there was an indication of softening with increasing irradiation temperature.

Embrittlement of Zircaloy-Clad Fuel Rods Irradiated Under Film Boiling Conditions
Embrittlement of Zircaloy-Clad Fuel Rods Irradiated Under Film Boiling Conditions

Author: RR. Hobbins

Publisher:

Published: 1979

Total Pages: 14

ISBN-13:

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Pressurized water reactor type fuel rods are being irradiated under postulated accident conditions in the Power Burst Facility at the Idaho National Engineering Laboratory as part of the Thermal Fuels Behavior Program. In these tests, film boiling was achieved by establishing a mismatch reactor power and coolant flow, while maintaining the coolant pressure at 15 MPa.

Handbook of Nuclear Engineering
Handbook of Nuclear Engineering

Author: Dan Gabriel Cacuci

Publisher: Springer Science & Business Media

Published: 2010-09-14

Total Pages: 3701

ISBN-13: 0387981306

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This is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all levels, this book provides a condensed reference on nuclear engineering since 1958.