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Asai, Shiho; Hanzawa, Yukiko; Konda, Miki; Suzuki, Daisuke; Magara, Masaaki; Kimura, Takaumi
no journal, ,
Various Zr isotopes generated by U fission are found in spent fuel and HLW. Among them, Zr which has a long half-life of 1.510y has a potential to contribute to radiation dose over an extended period of time after the implementation of HLW disposal. The inventory estimation of Zr in HLW confirmed by measured data is the key to realize a safe and cost-efficient disposal. In this study, a simple and robust analytical technique for the determination of Zr based on ion-exchange chromatography combined with ICP-MS was developed. Interference-free measurement was achieved by a single anion-exchange step, removing Sr, Nb, and Mo which would cause spectral interferences. Additionally, major component U and radioactive components, such as Cs, Ba, and Pu, were also removed concurrently. Concentration of Zr was readily calculated with measured isotope ratios of Zr/Zr in the sample and natural Zr-spiked sample with sufficient accuracy.
Yomogida, Takumi; Asai, Shiho; Saeki, Morihisa; Hanzawa, Yukiko; Esaka, Fumitaka; Oba, Hironori; Magara, Masaaki
no journal, ,
Inventory estimation of long-lived fission products (LLFPs) in high-level radioactive waste (HLW) is indispensable for the long-term safety assessment of geological repository. Reliability of the estimated inventory is verified with actual measurement values which are drawn from proven analytical techniques. There has been increasing interest in the development of new determination methods of Pd-107 which is one of the LLFPs with a half-life of 6.510 y because little measured data has been reported. Major difficulty in determination of Pd-107 involves the poor recovery of Pd in separation step required prior to measurement. In this study, a highly selective separation technique based on laser-induced microparticle formation has been applied to Pd separation. The recovery percentage of Pd from a simulated HLW solution were affected by irradiation time and laser pulse energy. The maximum recovery percentage of 60% was achieved by 20-min irradiation at the energy of 100 mJ.