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Journal Articles

Dissolution of powdered spent fuel and U crystallization from actual dissolver solution for "NEXT" process development

Nomura, Kazunori; Hinai, Hiroshi; Nakahara, Masaumi; Kaji, Naoya; Kamiya, Masayoshi; Oyama, Koichi; Sano, Yuichi; Washiya, Tadahiro; Komaki, Jun

Proceedings of 3rd International ATALANTE Conference (ATALANTE 2008) (CD-ROM), 5 Pages, 2008/05

Oral presentation

Dissolution of Pu solid sample on microwave heating, 1; Dissolution of PuO$$_{2}$$

Hinai, Hiroshi; Ichige, Yoshiaki; Aose, Shinichi

no journal, , 

no abstracts in English

Oral presentation

Dissolution of PuO$$_{2}$$ sample in high temperature by microwave heating

Hinai, Hiroshi; Ichige, Yoshiaki; Aose, Shinichi

no journal, , 

no abstracts in English

Oral presentation

Dissolution behavior of the irradiated fast reactor fuel powder; Influence of particle size

Hinai, Hiroshi; Tomita, Yutaka; Nomura, Kazunori; Oyama, Koichi; Kitajima, Takafumi; Koizumi, Tsutomu

no journal, , 

no abstracts in English

Oral presentation

Activities of practical training in Japan Nuclear Education Network (JNEN)

Yokoyama, Yoshitomo; Hinai, Hiroshi; Kato, Hiroshi; Ojima, Hisao

no journal, , 

no abstracts in English

Oral presentation

Improved spectrophotometric method for determination of hydrazine

Aihara, Haruka; Hinai, Hiroshi; Nakajima, Yasuo

no journal, , 

no abstracts in English

Oral presentation

Study on application of aqueous treatment for fuel debris in post severe accident, 3; Fundamental test on dissolution of MOX-Zry simulated debris by nitric acid

Ishihara, Miho; Hinai, Hiroshi; Nakamura, Masahiro; Yano, Kimihiko; Nakajima, Yasuo; Washiya, Tadahiro

no journal, , 

no abstracts in English

Oral presentation

Influence of impurities from spent fuel pool on solvent extraction process, 1; Behavior of impurities in solvent extraction system

Aihara, Haruka; Hinai, Hiroshi; Kitawaki, Shinichi; Nakajima, Yasuo; Taguchi, Katsuya

no journal, , 

no abstracts in English

Oral presentation

Research and development for radioactivity measurement of secondary waste from Fukushima Daiichi Nuclear Power Station; Study of analytic pretreatment for chelating resin

Fukuda, Yuhei; Arai, Yoichi; Suganuma, Takashi; Hinai, Hiroshi; Sano, Yuichi; Shibata, Atsuhiro; Nomura, Kazunori

no journal, , 

no abstracts in English

Oral presentation

Study of analytical method for secondary waste generated from the multi radionuclide removal system, 1; Study of analytical pretreatment method for ferrocyanide

Arai, Yoichi; Sano, Yuichi; Suganuma, Takashi; Hinai, Hiroshi; Ikeda, Akira*; Obata, Masamichi*; Shibata, Atsuhiro; Nomura, Kazunori

no journal, , 

no abstracts in English

Oral presentation

Characterization of secondary waste generated by Fukushima Daiichi Nuclear Power Station accident, 1; Particle size distribution measurement of slurry generated from Multi-Radionuclide Removal System

Fukuda, Yuhei; Suganuma, Takashi; Hinai, Hiroshi; Ikeda, Akira*; Obata, Masamichi*; Shibata, Atsuhiro; Nomura, Kazunori

no journal, , 

no abstracts in English

Oral presentation

Characterization of secondary waste generated by Fukushima Daiichi Nuclear Power Station accident, 2; Radiochemical analysis of slurry generated from multi-radionuclide removal system

Hinai, Hiroshi; Shinoda, Yoshiharu; Kurosawa, Akira; Ikeda, Akira*; Obata, Masamichi*; Shibata, Atsuhiro; Nomura, Kazunori

no journal, , 

no abstracts in English

Oral presentation

Characterization of secondary waste generated by Fukushima Daiichi Nuclear Power Station accident, 3; Analysis of slurry generated from multi-nuclide removal equipment

Fukuda, Yuhei; Suganuma, Takashi; Hinai, Hiroshi; Ikeda, Akira*; Obata, Masamichi*; Shibata, Atsuhiro; Nomura, Kazunori

no journal, , 

no abstracts in English

Oral presentation

Basic study on production of hydrogen gas by radiolysis of the carbonate slurry generated from the multi-radionuclide removal system

Arai, Yoichi; Hinai, Hiroshi; Koma, Yoshikazu; Ikeda, Akira*; Obata, Masamichi*; Shibata, Atsuhiro; Nomura, Kazunori

no journal, , 

no abstracts in English

Oral presentation

Research and development of a method to remove chloride ions from liquid waste including U and Pu

Tada, Kohei; Kitawaki, Shinichi; Watanabe, So; Hinai, Hiroshi; Shibata, Atsuhiro; Nomura, Kazunori

no journal, , 

no abstracts in English

Oral presentation

Characterization of secondary waste generated by Fukushima Daiichi Nuclear Power Station accident, 4; Characteristics comparison of the existing and additional multiple radio-nuclides removal system slurry

Fukuda, Yuhei; Hinai, Hiroshi; Shibata, Atsuhiro; Nomura, Kazunori; Ikeda, Akira*; Obata, Masamichi*; Ichikawa, Masashi*; Takahashi, Ryota*; Hirayama, Fumio*

no journal, , 

no abstracts in English

Oral presentation

Characterization of secondary waste generated by Fukushima Daiichi Nuclear Power Station accident, 5; Analysis of carbonate slurry sampled from high integrity container

Fukuda, Yuhei; Arai, Yoichi; Hinai, Hiroshi; Nomura, Kazunori; Ikeda, Akira*; Obata, Masamichi*; Ichikawa, Masashi*; Takahashi, Ryota*; Hirayama, Fumio*

no journal, , 

no abstracts in English

Oral presentation

Characterization of carbonate slurry generated from multi-radionuclide removal system in Fukushima Daiichi Nuclear Power Station

Hinai, Hiroshi; Arai, Yoichi; Fukuda, Yuhei; Kurosawa, Akira; Koma, Yoshikazu; Shibata, Atsuhiro; Nomura, Kazunori

no journal, , 

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$$times$$10$$^{7}$$ [Bq/cm$$^{3}$$]) was determined in the sample by the radioactive measurement, it is inferred that the contaminated water has been concentrate. And small amount of $$alpha$$-ray emitting nuclides were determined. As the result of ICP-AES, it is estimated that most of slurry occupy CaCO$$_{3}$$ and Mg(OH)$$_{2}$$. 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 $$mu$$m.

Oral presentation

Study on H$$_{2}$$ gas production by radiolysis of carbonate slurry generated from Multi-Radionuclide Removal System

Arai, 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.

Oral presentation

Development of a method to treat the radioactive liquid waste containing chloride ions generated by Pyroprocessing

Tada, Kohei; Kitawaki, Shinichi; Watanabe, So; Hinai, Hiroshi; Shibata, Atsuhiro; Nomura, Kazunori

no journal, , 

no abstracts in English

41 (Records 1-20 displayed on this page)