[en] Short communication

[en] Short communication. 6 refs

[en] Published in summary form only

[en] The results are summed up of measuring ⁹⁰Sr concentration in gaseous effluents of two WWER-440 reactors in the V-1 nuclear power plant at Jaslovske Bohunice, for the years 1985-1987. Samples were taken from air filters in the stack. Aerosol particles had been cumulating in the filters for two to seven days. The sample beta activity was measured using an Intertechnique RA 12 low-background anticoincidence counter. The ⁹⁰Sr concentrations in the period under study ranged between 6.7 and 483.0 μBq/m³. The total annual ⁹⁰Sr discharges in the years 1985-1987 showed the following values: 427.6, 448.8 and 126.6, respectively. (Z.M.). 3 tabs., 6 refs

[en] The concentration of ^239,240Pu and ²³⁸Pu in airborne effluents in the years 1985-1987 from two reactors (total power 880 MW) of a nuclear power plant V-1 in Jaslovske Bohunice, Czehoslovakia, was determined. The concentration of ^239,240Pu in effluents ranged from 1.0 to 30.8 μBq.m^-3 and of ²³⁸Pu from 1.6 to 41.1 μBq.m^-3. The activity ratio ²³⁸Pu/^239,240Pu in airborne effluents kept within the range of 1.0-2.4. Total annual discharged activities of ^239,240Pu in 1985, 1986 and 1987 were 28.5, 12.7 and 12.2 kBq, respectively. Those of ²³⁸Pu in 1986 and 1987 were 16.6 and 15.1 kBq, respectively. (author) 11 refs.; 3 tabs

[en] Two radiochemical methods were used in parallel to determine ²⁴¹Am in the urine and feces of a person who had been internally contaminated with that radionuclide 25 years before. Both methods used feces and urine mineralizates. The first method comprised coprecipitation of Am together with alkaline earth metals by using bismuth phosphate, single separation on a catex, double separation on an anex, and extraction of Am into TTA in benzene. The other method consists of double coprecipitation of Am, viz., with calcium oxalate and with Fe(OH)₃, followed by double separation on an anex and a single separation on a catex. In both methods, ²⁴³Am served as the recovery indicator and in the preparation of electrodeposition samples. The samples were measured by alpha spectrometry using PIPS detectors

[en] Published in summary form only

[en] Published in summary form only

[en] Published in summary form only

[en] The National Radiation Protection Institute has been engaged in international comparisons organized by the French organization PROCORAD (Association pour la promotion du controle de qualite des analyses medicale en radiotoxicologie). The events encompassed the following topics: determination of ⁹⁰Sr, gamma spectrometry, uranium, actinides except uranium and tritium in urine; actinides in stool ashes, and a 'sample with surprise', i.e. urine with any radionuclide. The total results are compared with those obtained by the Institute