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Report No.

Study of radiation control method for Am- MOX fuel producing facility, 2; By analysis of nuclide composition ratio etc.

Takashima, Hideki ; Iwasa, Atsutoshi; Eguchi, Kazutoshi; Yoshimochi, Hiroshi; Obayashi, Hiroshi ; Emori, Shuichi

In Alpha-$$gamma$$ Facility (AGF),Japan Atomic Energy Agency Oarai, the situation of the existing nuclide composition ratio etc. has changed greatly by manufacturing of the Am content mixed oxide fuel and executing the characteristic test. Therefore, the nuclide composition ratio etc. concerned were measuring analyzed, and the radiation management method in the emergency was examined as a result. As for the analysis sample, it gathered in the cell and the glove box (17 places) in facility, and the nuclide composition ratio was evaluated from the measurement result of the mass spectrometry etc. As a result, the nuclide composition approximated to the MA fuel pellet was seen of many sample and the difference was seen in the nuclide composition of each sample (especially, Am-241, Pu-239, and Pu-240). The result of the radiation management method in the emergency becomes as follows from these. (1) It is possible to execute immediately the initial assessment of internal expose from these data obtained this time and all alpha radioactivity that can be measured comparatively promptly by the presumption evaluation of radioactivities of each nuclides such as Pu and Am on the accident generation place. (2) If happened an abnormal discharge and the air contamination etc. of A radioactive substance, the originating place and the nuclide composition can be presumed by evaluating the $$gamma$$ radioactivity of Am-241 and all alpha radioactivity that can be measured comparatively promptly.



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