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Rough localization of defective PWR fuel rods on the basis of the concentration ratio134Cs/137Cs in the primary coolant

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Abstract

The search for fuel assemblies with defective fuel rods by sipping tests involves expensive prolongations of the refuelling periods in nuclear power plants. It is attempted to reduce the number of fuel assemblies to be checked by sipping during the refuelling periods by means of rough localization of the defects on the basis of the fission product concentration ratio134Cs/137Cs in the primary coolant already during reactor operation. First results obtained in two examples of application at VVER type reactors are encouraging. The burnup of the defective assemblies could be correctly predicted from the cesium ratio in these two cases, which was confirmed by sipping tests after reactor shutdown.

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Authors and Affiliations

  1. Central Institute for Nuclear Research, Rossendorf, P.O. Box 19, DDR-8051, Dresden, (GDR)

    H. Zänker & R. Berndt

Authors
  1. H. Zänker
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  2. R. Berndt
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Zänker, H., Berndt, R. Rough localization of defective PWR fuel rods on the basis of the concentration ratio134Cs/137Cs in the primary coolant. Journal of Radioanalytical and Nuclear Chemistry, Articles 122, 239–244 (1988). https://doi.org/10.1007/BF02037766

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  • DOI: https://doi.org/10.1007/BF02037766

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