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The irradiation behavior of atomized U-Mo alloy fuels at high temperature

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Abstract

Post-irradiation examinations of atomized U-10Mo, U-6Mo, and U-6Mo-1.7Os dispersion fuels from the RERTR-3 experiment irradiated in the Advanced Test Reactor (ATR) were carried out in order to investigate the fuel behavior of high uranium loading (8 gU/cc) at a high temperature (higher than 200°C). It was observed after about 40 at% BU that the U-Mo alloy fuels at a high temperature showed similar irradiation bubble morphologies compared to those at a lower temperature found in the RERTR-1 irradiation result, but there was a thick reaction layer with the aluminum matrix which was found to be greatly affected by the irradiation temperature and to a lesser degree by the fuel composition. In addition, the chemical analysis for the irradiated U-Mo fuels using the Electron Probe Micro Analysis (EPMA) method were conducted to investigate the compositional changes during the formation of the reaction product.

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Authors and Affiliations

  1. Korea Atomic Energy Research Institute, 150 Dukjin-Dong Yusung-ku, 305-353, Taejon, Korea

    Jong-Man Park, Ki-Hwan Kim & Chang-Kyu Kim

  2. Argonne National Laboratory, 9700 South Cass Avenue, 60439-4815, Argonne, Illinois, USA

    M. K. Meyer, G. L. Hofman & R. V. Strain

Authors
  1. Jong-Man Park
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  2. Ki-Hwan Kim
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  3. Chang-Kyu Kim
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  4. M. K. Meyer
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  5. G. L. Hofman
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  6. R. V. Strain
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Additional information

This article based on a presentation made in the “Symposium on Nuclear Materials and Fuel 2000” held at the Korea Atomic Energy Research Institute (KAERI), Taejon, Korea, August 24–25, 2000 under the auspices of the Ministry of Science and Technology (MOST).

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Park, JM., Kim, KH., Kim, CK. et al. The irradiation behavior of atomized U-Mo alloy fuels at high temperature. Met. Mater. Int. 7, 151–157 (2001). https://doi.org/10.1007/BF03026953

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