Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 6; Numerical simulation analysis of relationships between nuclide inventory and solidified body temperature

Hiraki, Yoshihisa; Terasawa, Toshiharu*; Imaizumi, Ken*; Taniguchi, Takumi ; Kato, Jun ; Osugi, Takeshi ; Sone, Tomoyuki ; Nakazawa, Osamu ; Kuroki, Ryoichiro

The relationship between the amount of radionuclide to be solidified and the solidified body temperature was analyzed, when solidify contaminated water management waste at Fukushima Daiichi Nuclear Power Station with cement etc. at low temperature. The analysis code used the radiation transport code and the thermal analysis code. Thus, the limit value by radionuclide concentration during solidification process are evaluated. The summary of the test and some of the obtained results are introduced.

Language	:	Japanese
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Meeting title	:	日本原子力学会2019年秋の大会
Held date	:	2019/09
Location (city)	:	富山
Location (country)	:	日本
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Keywords	:	シミュレーション; インベントリ; セメント固化; AAM固化; 温度制限値; 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	:	太平洋コンサルタント; 電力中央研究所

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Registration No. : BB20190595
JAEA Abstracts No. :
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