Radioanalytical methods for sequential analysis of actinide isotopes in activated carbon filter-bed waste
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Radioanalytical methods for sequential analysis of actinide isotopes in activated carbon filter‑bed waste Bianca Geraldo1 · Leandro Goulart de Araujo1 · Roberto Vicente1 · Maria Helena Tirollo Taddei2 · Sandra Maria Cheberle2 · Júlio Takehiro Marumo1 Received: 5 June 2020 / Accepted: 29 September 2020 © Akadémiai Kiadó, Budapest, Hungary 2020
Abstract In this work, we compare methods for the sequential determination of U and the transuranium elements Np, Pu, Am, and Cm. The chemical yield, the time spent in the analysis, the amount of secondary waste, and the costs of each method are the aspects of interest. Two methods were compared: extraction chromatography (EC) and ion exchange plus extraction chromatography (IE + EC). The chemical yields of (EC) and (IE + EC) were similar for all radionuclides. The (EC) method is the more effective with respect to time of analysis, the amount of secondary waste and costs. Keywords Radioactive waste · Radiochemistry · Difficult to measure radionuclides · Cost–benefit analysis
Introduction IEA-R1 is a nuclear research reactor situated at the Nuclear and Energy Research Institute (IPEN) in Sao Paulo, Brazil. Various radioactive wastes are routinely generated, including replaced filter beds with activated carbon used in the cooling water primary circuit purification system. This filter is used to remove the radioactive material dissolved in water that is retained neither in the cartridge filters nor the ion-exchange resins, the other two filter types of the system. The control of the water quality is made by measurements of water conductivity and the concentration of radioactive material. When the parameters are outside the established limit, the ion-exchange resins are regenerated and the carbon beds backflushed. If these treatments fail in restoring Electronic supplementary material The online version of this article (https://doi.org/10.1007/s10967-020-07435-8) contains supplementary material, which is available to authorized users. * Leandro Goulart de Araujo [email protected] 1
Gerência de Rejeitos Radioativos (GRR), Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), Av. Prof. Lineu Prestes, 2242, Cidade Universitária, São Paulo, SP CEP 05508‑000, Brazil
Laboratório de Poços de Caldas (LAPOC/CNEN-MG), Rodovia Poços de Caldas – Andradas, Km 13, Poços de Caldas, MG CEP 37701‑970, Brazil
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operational conditions, the filter beds are replaced and collected as solid radioactive waste. The radionuclides of most radiological significance, that are present in the wastes generated by the nuclear research reactor, are a) fission products such as 3H, 14C, 90Sr, 99Tc, 129 134 I, Cs, and 137Cs; b) activation products such as 54Mn, 55 Fe, 60Co, 59Ni and 63Ni; c) the natural isotopes of U; and d) the actinides 237Np, 238Pu, 239Pu, 240Pu, 241Am, 242Cm and 244Cm. Many of them are known as Difficult To Measure Radionuclides (DTM). There are two main reasons for such denomination. Firstly, they do not emit measurable gamma radiation in their nuclear decay proc
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