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Hashizume, Shuji; Matsumoto, Junko; Bamba, Tsunetaka
Zairyo To Kankyo, 47(10), p.638 - 644, 1998/00
no abstracts in English
Wada, Ryutaro*; Nishimura, Tsutomu*; Fujiwara, Kazuo*; *; *
PNC TJ1058 97-003, 33 Pages, 1997/03
None
Arai, Yoichi; Hinai, Hiroshi; Koma, Yoshikazu; Ikeda, Akira*; Obata, Masamichi*; Shibata, Atsuhiro; Nomura, Kazunori
no journal, ,
no abstracts in English
gas production by radiolysis of carbonate slurry generated from Multi-Radionuclide Removal SystemArai, Yoichi; Hinai, Hiroshi; Koma, Yoshikazu; Shibata, Atsuhiro; Nomura, Kazunori
no journal, ,
Multi-Radionuclide Removal System (MRRS) has been utilized for decontaminate of the radioactive contaminated water in Fukushima Daiichi Nuclear Power Station (1F). The secondary wastes including iron hydroxide, carbonate and used adsorbents are packed in the High Integrity Container (HIC). It was reported that the radioactive liquid was overflowed in several HICs. This phenomenon was only observed in HICs containing the carbonate slurry waste. It was inferred that volume increase of wastes due to gas generation caused by the water radiolysis. However, the gas generation behavior was not well known. Therefore, it is important to investigate gas generation behavior of radioactive carbonate slurry waste. Ten ml of the carbonate slurry waste was put into the sealing vial. After standing sample for certain duration, concentration of hydrogen was measured by gas-chromatography. Total amounts of hydrogen gas produced from the slurry was proportionally increased with time. Measured G-value was equivalent to the theoretical G value. This result showed that hydrogen gas generated by water radiolysis in radioactive carbonate slurry waste.
Meguro, Yoshihiro
no journal, ,
From contaminated water treatment systems at Fukushima Daiichi Nuclear Power Station, various radioactive wastes have been generated and stored. Especially, concentrated waste liquid, iron hydroxide slurry and carbonate slurry contain high concentration of strontium-90 and a large amount of water and sea water components. Therefore, when these wastes are stored for a long period, the risk of leakage of radioactive waste due to corrosion of storage containers and burning of hydrogen gas generated by radiolysis increases. In this research, we are developing technology to solidify these wastes using phosphate solidification materials. We are trying suppressing the generation of hydrogen gas by performing heat dehydration at the time of curing of the solidified material and to fix Sr and seawater component by making poorly water-soluble stable compounds.
