Non-destructive control of the plutonium content of spent fuel under uncertainties on irradiation history
Author(s) -
V. I. Savander,
V. B. Glebov
Publication year - 1998
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/296652
Subject(s) - plutonium , mox fuel , plutonium 240 , spent nuclear fuel , nuclear engineering , uranium , spent fuel pool , nuclear reactor core , burnup , nuclear fuel , environmental science , enriched uranium , waste management , plutonium 239 , radiochemistry , materials science , engineering , chemistry , nuclear physics , fission , physics , metallurgy , neutron
It is apparent that serious attention must be given to the use of weapons-grade plutonium in fuel cycles in nuclear power plants. It is becoming increasingly necessary to organize a mixed fuel cycle which would be presumed to have ordinary, low-enriched uranium fuel and weapons-grade plutonium fuel in a one-time reactor core loading. This research examined the problem of how to detect the possible substitution of a low-enriched uranium bundle for a bundle containing weapons-grade plutonium. Final determination of fuel assembly substitution was made using a non-destructive control methodology, which was based on gamma-spectra analysis of spent fuel for initial fuel composition identification
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