Release Fractions for Nuclides in Transport Safety Analysis of Spent Fuel Transport Cask

MA Xinyu, ZHANG Bairu, ZUO Shuchun

Packaging Engineering ›› 2025, Vol. 46 ›› Issue (11) : 330-340.

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Packaging Engineering ›› 2025, Vol. 46 ›› Issue (11) : 330-340. DOI: 10.19554/j.cnki.1001-3563.2025.11.036
Equipment Protection

Release Fractions for Nuclides in Transport Safety Analysis of Spent Fuel Transport Cask

  • MA Xinyu, ZHANG Bairu, ZUO Shuchun
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Abstract

The work aims to summarize and discuss the sources, values, and conservativeness of radionuclide release fractions used in the safety analysis of containment systems for spent fuel transportation casks so as to provide a reference for research and development of spent fuel transportation casks. Initially, the technical standards and research reports involving radionuclide release fractions internationally were outlined, and then classified by the types of radionuclides. Additionally, the conservativeness of radionuclide release fraction data was analyzed in conjunction with relevant literature. Most of release fractions of radionuclides were determined through experiments. However, due to differences in fuel conditions and methods used to process the experimental data, the release fraction values for same radionuclide may vary across different reports. When conducting safety analysis for the containment system of casks used in the transport of commercial spent fuel, the calculation processes and release fraction data stipulated in ISO 12807 and ANSI N14.5 are all acceptable. In contrast, the assumptions of ANSI N14.5 are more conservative. It is assumed that the release fraction of fission gases is 0.3, the release fraction of volatiles is 2×10-4, the release fraction of fines is 3×10-5, and the fraction of crud that spalls-off of rods is 0.15 under normal transport conditions. These assumptions are supported by experimental data and can ensure transport safety.

Key words

containment system / activity release / release fractions

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MA Xinyu, ZHANG Bairu, ZUO Shuchun. Release Fractions for Nuclides in Transport Safety Analysis of Spent Fuel Transport Cask[J]. Packaging Engineering. 2025, 46(11): 330-340 https://doi.org/10.19554/j.cnki.1001-3563.2025.11.036

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