Fast neutrons from reactor fuel were monitored with CR-39 track detectors, using energy discrimination by shape selection to reduce the number of disturbing events. The detectors were irradiated in a steel container placed on the top of assemblies. Exposure time was optimized for providing acceptable statistics and keeping γ-dose low enough -below 6 kGy - to prevent the material from damage due to the huge intensity γ-background. As the effect of the adjacent assemblies in a hexagonal lattice of 160 mm storage distance is rather high, individual assay on isolated fuel assemblies is recommendable.

Tam N.C., Baricza K., Lakosi L.

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Từ khóa : Assays; Dosimetry; Gamma rays; Nuclear reactors; Particle beam tracking; Polycarbonates; Radiation damage; Spent fuels; Polyallyldiglycol carbonate; Polymeric track detectors; Neutron detectors