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V. V. Frolov (1989)
Nuclear-Physical Methods for Monitoring Fissile Materials
M. Arnautova, Y. Kandiev, B. Lukhminsky, G. Malishkin (1993)
Monte Carlo simulation in nuclear geophysics. Intercomparison of the PRIZMA Monte Carlo program and benchmark experimentsThe International journal of radiation applications and instrumentation. Part E. Nuclear geophysics, 7
V. N. Kolobashkin, P. M. Ruzhanskii, V. D. Sidorenko (1983)
Handbook of the Radiation Characteristics of Irradiated Nuclear Fuel
M. A. Arnautova, Ya. Z. Kandiev, B. E. Lukhminsky, G. N. Malishkin (1993)
Monte Carlo simulation and nuclear geophysics. In comparison of the PRIZMA Monte Carlo program and benchmark experimentsNucl. Geophys., 7
An approach is proposed for validating the nuclear and radiation safety of a container for spent fuel assemblies from AMB-100 and-200 reactors at the Beloyarskaya nuclear power plant. To validate the radiation safety, the characteristics of fuel assemblies and their classification according to the average fuel burnup in the casing, and the intensities of n and γ radiation in the casing are analyzed. Nuclear safety is validated on the basis of the concept of a “model” casing. This model makes it possible to obtain an upper estimate of the effective coefficient of neutron multiplication for all real casings with fuel assemblies. Calculations are used to determine the minimum necessary thickness of the vessel, bottom, and cover for 17-and 35-place casings. It is shown that no special neutron protection is needed. The container design to be developed meets the IAEA and OPBZ-83 safety standards.
Atomic Energy – Springer Journals
Published: Sep 23, 2006
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