Artigo de peri??dico
Inventorying the radionuclides in spent cartridge filters from the primary circuit of a nuclear research reactor by the dose-to-activity method
Registro en:
0969-806X
171
10.1016/j.radphyschem.2020.108710
66.43
72.00
Autor
TESSARO, ANA P.G.
ARAUJO, LEANDRO G. de
VICENTE, ROBERTO
Resumen
The high activity of spent cartridge filters from the cooling water polishing system of a nuclear research reactor
precludes, in routine work of a waste characterization program, the usual method of radiochemical analysis of
filter samples. For this waste, the dose-to-activity method, using a gamma spectrometer and a dose rate meter, is
an alternative for the determination of the activities of the gamma emitters with acceptable accuracy. The ratio
of photon peak-areas from different radionuclides, corrected by the detector energy-dependent efficiency, allowed
estimating the proportions between the activities of the different radionuclides present. Finally, the simulation
of the counting geometry, using the point-kernel method to estimate the air dose rate resulting from an
arbitrary concentration of those radionuclides and the comparison of the calculated with the measured air dose
rate have yielded the needed estimates of the activity concentrations. The aim of this paper is to report the
development of the method applied for the determination of the concentration of the gamma-emitters present in
cartridge filters from the IEA-R1 Nuclear Research Reactor.