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Destructive Analysis Determination of Neutron Emission from Spent RBMK Fuel

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Abstract

Absolute calibration of the UNIT-10m setup on the basis of the results obtained by destructive analysis is examined. The calibration procedure consists in performing measurements using the SKAT laboratory test stand at the Radium Institute with a model unirradiated assembly and neutron sources with known intensity, simulating neutron emission, comparing experimental data and calculations for certain reference points. The data obtained from destructive analysis can be used to establish a relation between the neutron flux of an irradiated assembly and the parameters being determined (fuel burnup, content of the main fissioning isotopes).

A relation is presented between burnup and accumulation of the main neutron-emitting isotopes in spent RBMK fuel. The data were obtained by radiochemical and α- and mass-spectrometric methods. The total neutron emission is determined taking account of the neutron yield from spontaneous-fission reactions of even isotopes of plutonium and curium and from (α, n) reactions.

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Authors and Affiliations

  1. V. G. Khlopin Radium Institute, Russia

    A. G. Korenkov, T. P. Makarova, A. V. Stepanov, E. V. Pevtsova, B. N. Belyaev & A. A. Voronkov

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  1. A. G. Korenkov
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  2. T. P. Makarova
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  3. A. V. Stepanov
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  4. E. V. Pevtsova
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  5. B. N. Belyaev
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  6. A. A. Voronkov
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Korenkov, A.G., Makarova, T.P., Stepanov, A.V. et al. Destructive Analysis Determination of Neutron Emission from Spent RBMK Fuel. Atomic Energy 93, 815–822 (2002). https://doi.org/10.1023/A:1022033528105

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  • DOI: https://doi.org/10.1023/A:1022033528105

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