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Sato, Junya; Kikuchi, Hiroshi*; Kato, Jun; Sakakibara, Tetsuro; Matsushima, Ryotatsu; Sato, Fuminori; Kojima, Junji; Nakazawa, Osamu
QST-M-8; QST Takasaki Annual Report 2016, P. 62, 2018/03
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Fukuda, Yuhei; Arai, Yoichi; Suganuma, Takashi; Hinai, Hiroshi; Sano, Yuichi; Shibata, Atsuhiro; Nomura, Kazunori
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Arai, Yoichi; Sano, Yuichi; Suganuma, Takashi; Hinai, Hiroshi; Ikeda, Akira*; Obata, Masamichi*; Shibata, Atsuhiro; Nomura, Kazunori
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Fukuda, Yuhei; Suganuma, Takashi; Hinai, Hiroshi; Ikeda, Akira*; Obata, Masamichi*; Shibata, Atsuhiro; Nomura, Kazunori
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Hinai, Hiroshi; Shinoda, Yoshiharu; Kurosawa, Akira; Ikeda, Akira*; Obata, Masamichi*; Shibata, Atsuhiro; Nomura, Kazunori
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Fukuda, Yuhei; Suganuma, Takashi; Hinai, Hiroshi; Ikeda, Akira*; Obata, Masamichi*; Shibata, Atsuhiro; Nomura, Kazunori
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Arai, Yoichi; Hinai, Hiroshi; Koma, Yoshikazu; Ikeda, Akira*; Obata, Masamichi*; Shibata, Atsuhiro; Nomura, Kazunori
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Komada, Ryo*; Yabe, Yuki*; Arai, Tsuyoshi*; Sato, Fuminori; Kojima, Junji
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Fukuda, Yuhei; Hinai, Hiroshi; Shibata, Atsuhiro; Nomura, Kazunori; Ikeda, Akira*; Obata, Masamichi*; Ichikawa, Masashi*; Takahashi, Ryota*; Hirayama, Fumio*
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Fukuda, Yuhei; Arai, Yoichi; Hinai, Hiroshi; Nomura, Kazunori; Ikeda, Akira*; Obata, Masamichi*; Ichikawa, Masashi*; Takahashi, Ryota*; Hirayama, Fumio*
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Hinai, Hiroshi; Arai, Yoichi; Fukuda, Yuhei; Kurosawa, Akira; Koma, Yoshikazu; Shibata, Atsuhiro; Nomura, Kazunori
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Multi-Radionuclide Removal System (MRRS) has been operating to decontaminate the contaminated water in Fukushima Daiichi Nuclear Power Station. MRRS consist of pretreatment facilities (Iron coprecipitation treatment facility and Carbonate precipitation treatment facility) and adsorption towers. This system is able to remove most of the radioactive materials except Tritium. However, Associated with a this process, the secondary radioactive wastes (slurry, spent adsorbent) were generated and stored temporary in the High Integrity Container (HIC). It is necessary to various properties investigation for the inventory evaluation and future disposal. Therefore, the carbonate slurry samples were transported from Fukushima Daiichi Nuclear Power Station to our laboratories in Tokai-mura and analyzed. High concentration of Sr-90 (1.3
10
[Bq/cm
]) was determined in the sample by the radioactive measurement, it is inferred that the contaminated water has been concentrate. And small amount of 
-ray emitting nuclides were determined. As the result of ICP-AES, it is estimated that most of slurry occupy CaCO
and Mg(OH)
. These obtained data showed that decontamination system is operating normally. Also, the particle size of the slurry was analyzed by image analyzing method. The particles of slurry was found to have a median particle diameter of several 
m.
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.
Sato, Junya; Suzuki, Shinji*; Kato, Jun; Sakakibara, Tetsuro; Meguro, Yoshihiro; Nakazawa, Osamu
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Komada, Ryo*; Yoshikawa, Yuta*; Arai, Tsuyoshi*; Sato, Fuminori; Kojima, Junji
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Hinai, Hiroshi; Shibata, Atsuhiro; Nomura, Kazunori
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Multi-Radionuclide Removal System (MRRS) has been operating to decontaminate the contaminated water in Fukushima Daiichi Nuclear Power Station. Although this system removes most of the radioactive materials, significant amount of secondary radioactive wastes (slurry, spent adsorbent) were generated subsequently to the treatment. In particularly, because of the high radioactivity and the abundance of generation amount, the carbonate slurry waste is required to characterize preferentially. It is necessary to various properties investigation for selecting suitable treatment and disposal methods. Therefore, the carbonate slurry samples taken from the MRRS were transferred from Fukushima Daiichi Nuclear Power Station to the Chemical Processing Facility (CPF) in Nuclear Fuel Cycle Engineering Laboratories of Japan Atomic Energy Agency (JAEA), and was analyzed for radioactivity, amount of element composition and particle size distribution. The radioactive analysis showed that the main nuclides of carbonate slurry were Sr-90/Y-90. In addition, small amount of alpha-ray emitting nuclides was determined. As the result of elemental analysis, it is estimated that most of slurry are composed by CaCO and Mg(OH). The median particle diameter of carbonate slurry samples was found to be several micrometre.
Nitta, Ayako; Hinai, Hiroshi; Ichige, Yoshiaki; Koma, Yoshikazu; Shibata, Atsuhiro
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Kato, Tomoaki; Yamagishi, Isao
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Yamagishi, Isao; Kato, Tomoaki; Horita, Takuma
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Kato, Tomoaki; Yamagishi, Isao
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