Publication | Open Access
Non-Destructive Gamma-Ray Spectrometry on Spent Fuels of a Boiling Water Reactor
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1975
Year
Jpdr-i ReactorNuclear Waste ManagementNuclear PhysicsEngineeringNuclear DataIrradiation HistoryReactor PhysicsChemistryReactor AnalysisChemical EngineeringNon-destructive Gamma-ray SpectrometryNuclear FissionBoiling Water ReactorAnalytical ChemistryNuclear MaterialsRadiation ChemistryNuclear ReactorsFuel Storage PoolNuclear EngineeringNuclear EnergyRadioactive Waste DisposalSpent FuelsNuclear Fuel BurnupNatural SciencesNuclear SafetyRadioanalytical ChemistryChemical Kinetics
The spent fuels from the JPDR-I reactor were measured by means of a γ-scanning facility installed in the fuel storage pool. The spatial distributions of the fission products (134Cs and 137Cs) were measured and analyzed in reference to the effects of control rod pattern. The ratios holding between the products of neutron capture and of direct fission (134Cs/137Cs and 154Eu/137Cs) were also examined for its relevance to non-destructive burnup determination. The activity ratios of the fission products can be expressed by a linear function of burnup, provided that corrections are made to account for differences in irradiation history and for spatial variations in the neutron spectrum.