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Measurement and burnup analysis of $$^{106}$$Ru/$$^{144}$$Ce activity ratio for spent fuel cooled more than 10 years

Sato, Shunsuke*; Nauchi, Yasushi*; Hayakawa, Takehito*; Kimura, Yasuhiko; Suyama, Kenya

It is difficult to measure $$gamma$$-ray from short half-life nuclides such as $$^{106}$$Ru-106 and $$^{144}$$Ce in used fuel with more than 10 year cooling time. In this study, we make it possible to measure $$gamma$$ radiation of these nuclides by changing detection efficiency with install of polyethylene block. We obtained good agreement of activity ratio of $$^{106}$$Ru/$$^{144}$$Ce between measurement and calculation.

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