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.

Language	:	Japanese
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Meeting title	:	日本原子力学会2021年秋の大会
Held date	:	2021/09
Location (city)	:	札幌(online)
Location (country)	:	日本
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Keywords	:	MOX; $^{241}$ Am; ガンマ線; 遮蔽材; 遮蔽性能解析; 放射線計測
Research Facility	:	プルトニウム燃料製造施設
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Registration No. : BB20210221
JAEA Abstracts No. :
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