FIELD: physics.
SUBSTANCE: invention relates to a method for monitoring the fuel rod cladding of spent fuel assemblies (SFA) of transport nuclear power plants. In the claimed method, the SFA is placed in a sealed pencil filled with a gas coolant, heated with a sump with SFA, and the gas coolant is pumped out with radioactive gases leaving the SFA and a pair of residual moisture along a closed circulation circuit in series through an aerosol filter, an iodine-selective filter, a bubbler filled with an alkali solution, and a measuring chamber. They separate the radionuclides 137Cs on the aerosol filter, 129I - on the selective filter, 14C and residues 129I - in the alkaline solution of the bubbler. Further, beta-radiometric measurements 85Kr in the gas coolant, the measured radionuclide activity values 85Kr with the established criteria for rejecting the defective fuel rods of spent fuel assemblies and determine the tightness of the fuel rod claddings of SFA.
EFFECT: increased accuracy of determining the volume beta activity 85Kr in the gas coolant of heated SFA.
3 cl, 1 dwg, 4 tbl, 2 ex
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Authors
Dates
2017-06-13—Published
2016-05-26—Filed