I-129 DETERMINATION IN EVAPORATOR CONCENTRATE USING  OXIDATIVE EXTRACTION AND CHROMATOGRAPHIC RESIN

Thiago César de Oliveira; Roberto Pellacani Guedes Monteiro; Geraldo Frederico Kastner; Arno Heeren de Oliveira

doi:10.15392/bjrs.v9i1A.1248

Authors

Thiago César de Oliveira Universidade Federal de Minas Gerais - UFMG Departamento de Engenharia Nuclear - DENU
Roberto Pellacani Guedes Monteiro Centro de Desenvolvimento da Tecnologia Nuclear - CDTN
Geraldo Frederico Kastner Centro de Desenvolvimento da Tecnologia Nuclear - CDTN
Arno Heeren de Oliveira Universidade Federal de Minas Gerais - UFMG Departamento de Engenharia Nuclear - DENU

DOI:

https://doi.org/10.15392/bjrs.v9i1A.1248

Keywords:

Iodine, Evaporator concentrate, Oxidative extraction, Chromatographic resin

Abstract

Determination of long-lived radionuclides is very important for study of the radioactive waste final deposition. In this work will be studied ¹²⁹I radionuclide which present 1.6 x 10⁷ years half-life, β-particle-emitting (E_max = 194 keV) and X-ray-emitting (E = 29.78 keV). It’s produced primarily from fission of ²³⁵U and ²³⁹Pu and for fission induced by thermal neutrons. For this reason, radiochemical procedures for ¹²⁹I determination in evaporator concentrate wastes from nuclear power plants were carried out. The first procedure was based on oxidative extraction and alkaline absorption and the second one, was based on selective extraction using a chromatographic resin in order to separate iodine from its interferents. After the separation steps, the iodine activity was measured by ultra low gamma spectrometry technique. To set up the yield recovery for ¹²⁹I, a tracer solution of ¹²⁹I was used in order to follow the behavior of iodine during the separation steps. The yield recovery for iodine was around 75-80% for the first procedure and 80-85% for the second. The two procedures used mutually, ensure a greater efficiency in the separation of iodine from their respective interferents.

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