2004•Atomic EnergyRequires access

Determination of the Fuel-Assembly Burnup in a Research Reactor by Repeated Short-Time Irradiation Followed by γ Spectrometric Measurements

A. V. Bushuev, A. F. Kozhin, G. Li, V. N. Zubarev, A. A. Portnov, V. P. Alferov, M. V. Shchurovskaya

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Key concepts: Burnup, Research reactor, Neutron flux, Nuclear engineering, Spent nuclear fuel, Nuclear fission product, Uranium, Fission products

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Determination of the Fuel-Assembly Burnup in a Research Reactor by Repeated Short-Time Irradiation Followed by γ Spectrometric Measurements — Research Paper | ScholarLens