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Measurement and calculation analysis of shielding material's performance for MOX containing americium

Okada, Toyofumi; Shibanuma, Tomohiro; Honda, Fumiya; Komeno, Akira ; Kikuno, Hiroshi

$$^{241}$$Am is generated by beta-decay of $$^{241}$$Pu. In the case of treating MOX, it is important for shielding about 60keV gamma-ray emitted by $$^{241}$$Am. Also getting dose rate data of MOX containing $$^{241}$$Am is valuable. In this work, we measured gamma-ray dose rate from MOX containing $$^{241}$$Am by changing thickness of shielding materials and range between MOX and measuring instruments. Also we confirmed that calculating analysis is useful for evaluation of shielding material's performance.

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