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Report No.

Development of determination methods for $$beta$$ ray emitting nuclides at CPF

Motoyama, Risa; Hinai, Hiroshi; Ichige, Yoshiaki; Shibata, Atsuhiro  ; Nomura, Kazunori  

Various properties of radioactive wastes generated at the Fukushima Daiichi Nuclear Power Station have been analyzed at Chemical Processing Facility (CPF) in Japan Atomic Energy Agency (JAEA) to contribute to their future treatment and disposal studies. The radioactive concentration of $$beta$$ ray emitting nuclides is one of the essential information as well as those of $$alpha$$ ray and $$gamma$$ ray emitting nuclides. It needs to develop separation and purification methods for each $$beta$$-emitter from unfamiliar mediums to the nuclear fuel cycle field. Due to the restrictions of the facility, these methods should avoid using halogen reagents. The steady analysis procedures of H-3, Sr-90 and I-129 have been already developed and in practice. Among them, the analysis method of I-129 will be presented and the determination method for Se-79 will be reported as issue currently under consideration.



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