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A setup for active neutron analysis of the fissile material content in fuel assemblies of nuclear reactors

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Abstract

An active neutron method for measuring the residual mass of 235U in spent fuel assemblies (FAs) of the IRT MEPhI research reactor is presented. The special measuring stand design and uniform irradiation of the fuel with neutrons along the entire length of the active part of the FA provide high accuracy of determination of the residual 235U content. AmLi neutron sources yield a higher effect/background ratio than other types of sources and do not induce the fission of 238U. The proposed method of transfer of the isotope source in accordance with a given algorithm may be used in experiments where the studied object needs to be irradiated with a uniform fluence.

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Authors and Affiliations

  1. National Research Nuclear University MEPhI, Kashirskoe sh. 31, Moscow, 115409, Russia

    A. V. Bushuev, A. F. Kozhin, T. B. Aleeva, V. N. Zubarev, E. V. Petrova & V. E. Smirnov

Authors
  1. A. V. Bushuev
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  2. A. F. Kozhin
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  3. T. B. Aleeva
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  4. V. N. Zubarev
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  5. E. V. Petrova
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  6. V. E. Smirnov
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Corresponding author

Correspondence to A. F. Kozhin.

Additional information

Original Russian Text © A.V. Bushuev, A.F. Kozhin, T.B. Aleeva, V.N. Zubarev, E.V. Petrova, V.E. Smirnov, 2015, published in Voprosy Atomnoi Nauki i Tekhniki, Seriya: Fizika Yadernykh Reaktorov, 2015, No. 5, pp. 47–53.

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Bushuev, A.V., Kozhin, A.F., Aleeva, T.B. et al. A setup for active neutron analysis of the fissile material content in fuel assemblies of nuclear reactors. Phys. Atom. Nuclei 79, 1362–1366 (2016). https://doi.org/10.1134/S1063778816080056

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  • DOI: https://doi.org/10.1134/S1063778816080056

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