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Abstract <p>The efficiency of the high-temperature treatment (HTT) of mixed uranium–plutonium nitride spent nuclear fuel (MUPN SNF) to separate the fuel compound from the cladding and remove volatile fission products from the fuel was evaluated. The high-temperature treatment of SNF allows separation of the fuel compound from the cladding. The degree of removal of cesium nuclides from the fuel compound does not exceed 7%, whereas tritium, radiocarbon, and ruthenium are removed from the fuel compound to 94.2, 89.9, and 95.5%, respectively, relative to their initial content in SNF.</p>

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High-Temperature Treatment of Mixed Uranium–Plutonium Nitride Spent Nuclear Fuel

  • 期刊论文

  • 发表日期：

    2025年12月1日

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  • V. N. Momotov,
  • D. E. Tikhonova,
  • A. O. Makarov,
  • A. Yu. Volkov,
  • M. V. Mazannikov,
  • A. M. Potapov,
  • Yu. P. Zaikov

摘要

Abstract

The efficiency of the high-temperature treatment (HTT) of mixed uranium–plutonium nitride spent nuclear fuel (MUPN SNF) to separate the fuel compound from the cladding and remove volatile fission products from the fuel was evaluated. The high-temperature treatment of SNF allows separation of the fuel compound from the cladding. The degree of removal of cesium nuclides from the fuel compound does not exceed 7%, whereas tritium, radiocarbon, and ruthenium are removed from the fuel compound to 94.2, 89.9, and 95.5%, respectively, relative to their initial content in SNF.