Performance of HT9 clad metallic fuel at high temperature

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Abstract

Irradiation testing and post-irradiation examination of HT9 clad U-10Zr metallic fuel has been carried out in the EBR-II reactor. Peak cladding temperatures in the range of 630 to 660°C were obtained in order to study high temperature breach behavior of metallic fuel. Of the 15 experimental fuel elements tested to 10 at% burnup, two breached by stress rupture. Breach behavior was found to be totally benign for reactor operations. Significant fuel/cladding chemical interactions involving lanthanide-series fission products and carbide depletion were observed in the hottest cladding region. © 1993.

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APA

Pahl, R. G., Lahm, C. E., & Hayes, S. L. (1993). Performance of HT9 clad metallic fuel at high temperature. Journal of Nuclear Materials, 204(C), 141–147. https://doi.org/10.1016/0022-3115(93)90210-P

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