Search Results - Darenskikh, O. G.

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    Fuel-burnup monitoring based on the characteristic neutron radiation of spent fuel assemblies

    Fuel-burnup monitoring based on the characteristic neutron radiation of spent fuel assemblies by Vlaskin, G. N., Chvankin, E. V., Darenskikh, O. G., Dzekun, E. G., Markin, E. G., Parfent'ev, E. A.

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    Monitoring homogeneous neutron absorbers during reprocessing of spent nuclear fuel

    Monitoring homogeneous neutron absorbers during reprocessing of spent nuclear fuel by Vlaskin, G. N., Renard, . V., Chvankin, E. V., Shumakov, A. V., Parfent'ev, E. A., Darenskikh, O. G., Markin, E. P.

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    Automatic determination of total quantity of substance in homogeneous media

    Automatic determination of total quantity of substance in homogeneous media by Bespyatykh, A. S., Darenskikh, O. G., Komissarov, A. V., Mel'nikov, V. D., Peskov, A. I., Tsenter, . M.

    Published in Measurement techniques
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