Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 13; Gamma-ray irradiation characteristics of solidified materials containing carbonate slurry

Kato, Jun ; Imaizumi, Ken*; Osugi, Takeshi ; Sone, Tomoyuki ; Kuroki, Ryoichiro ; Kikuchi, Michio*; Yamamoto, Takeshi*; Otsuka, Taku*; Kaneda, Yoshihisa*; Osawa, Norihisa*

Solidified cement and Alkali Activated Materials (AAM) containing simulated carbonated slurry was prepared, and the amount of Hydrogen gas generation on gamma-ray irradiation was determined. The obtained data was compared with the data of solidified material without any content of waste, and the effect for Hydrogen gas generation with the material containing simulated carbonated slurry was evaluated.

Language	:	Japanese
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Meeting title	:	日本原子力学会2020年秋の大会
Held date	:	2020/09
Location (city)	:	福岡(online)
Location (country)	:	日本
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Keywords	:	福島第一原子力発電所; 水処理二次廃棄物; 廃棄物固化; AAM; セメント固化; 福島第一原子力発電所事故; Fukushima Daiichi Nuclear Power Station Accident
Research Facility	:	ENTRY(地層処分基盤研究施設)
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Article of JAEA R&D Review	:
Cooperating Institute	:	国際廃炉研究開発機構

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Registration No. : BB20200166
JAEA Abstracts No. :
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