Browsing by Subject "NUCLEAR-WASTE"

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  • Aromaa, H.; Helariutta, K.; Ikonen, J.; Yli-Kaila, M.; Koskinen, L.; Siitari-Kauppi, M. (2018)
    A method for analyzing H-3, Cl-36, Na-22, Ba-133 and Cs-134 from simulated groundwater (SGW) samples was introduced. Gamma emitting radionuclides Na-22, Ba-133 and Cs-134 were measured by using an HPGe-detector. Beta emitting H-3 and Cl-36 were separated from gamma emitting Na-22, Ba-133 and Cs-134. AgCl precipitation was used for the separation of Cl-36 from SGW samples with yields of 98 +/- 2%. H-3 was separated by distillation with recoveries of 97 +/- 3%. This method was used for the determination of activity concentrations of H-3, Cl-36, Na-22, Ba-133 and Cs-134 in SGW samples collected from an in situ through diffusion experiment.
  • Leskinen, Anumaija; Salminen-Paatero, Susanna; Räty, Antti; Tanhua-Tyrkkö, Merja; Iso-Markku, Taneli; Puukko, Esa (2020)
    Determination of C-14, Fe-55, Ni-63 and gamma emitters in two different types of activated reactor pressure vessel (RPV) steel samples were carried out. The gamma emitters were analysed using HPGe detectors with ISOCS and standard geometry calibrations. Two radioanalytical procedures for the C-14, Fe-55, Ni-63 analysis were developed using inactive samples and activated samples were analysed using modified procedures. A Monte Carlo code was used for the modelling of the activation results. The obtained measured and calculated results were comparable.
  • Leskinen, Anumaija; Gautier, Celine; Räty, Antti; Kekki, Tommi; Laporte, Elodie; Giuliani, Margaux; Bubendorff, Jacques; Laurila, Julia Pauliina; Kurhela, Kristian Otto Aleksi; Fichet, Pascal; Salminen-Paatero, Susanna (2021)
    This paper reports the results obtained in a Nordic Nuclear Safety Research project during the second intercomparison exercise for the determination of difficult to measure radionuclides in decommissioning waste. Eight laboratories participated by carrying out radiochemical analysis of H-3, C-14, Cl-36, Ca-41, Fe-55 and Ni-63 in an activated concrete. In addition, gamma emitters, namely Eu-152 and Co-60, were analysed. The assigned values were derived from the submitted results according to ISO 13,528 standard and the performance assessments were determined using z scores. The measured results were compared with activation calculation result showing varying degree of comparability.