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Report No.

Feasibility study of Pu monitoring technology for Pu solution with FP; Evaluation of $$gamma$$ rays spectrum by simulation at the concrete cell

Sekine, Megumi; Matsuki, Takuya ; Yamanaka, Atsushi ; Nakamura, Hironobu ; Tomikawa, Hirofumi

Plutonium (Pu) solution and solid waste containing fission products (FP) are stored in a reprocessing plant as inventory or retained waste. It is difficult to access the Pu solution with FP since it has an extremely high radiation dose rate, and there is no direct Pu solution continuous monitoring /verification technology. From a viewpoint of ensuring nuclear transparency, Japan Atomic Energy Agency (JAEA) has started to develop a new technology using non-destructive assay to measure and monitor Pu solution with FP since JFY 2015. In this poster presentation, model of storage tank/concrete cell for high radioactive liquid waste (HALW), and evaluation of $$gamma$$ ray spectra and the distribution of radiation dose rate based on actual HALW analysis results are presented. This project has been carried out under the support of the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of the Japanese government.



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