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Warashina, Tomoro*; Sato, Asako*; Hinai, Hiroshi; Shaikhutdinov, N.*; Shagimardanova, E.*; Mori, Hiroshi*; Tamaki, Satoshi*; Saito, Motofumi*; Sanada, Yukihisa; Sasaki, Yoshito; et al.
Applied and Environmental Microbiology, 90(4), p.e02113-23_1 - e02113-23_23, 2024/04
Times Cited Count：0 Percentile：0.00(Biotechnology & Applied Microbiology)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
; Hinai, Hiroshi; Shigetome, Yoshiaki; Kono, Shusaku;
JNC TN8410 2003-002, 29 Pages, 2003/02
Japan Nuclear Cycle Development institute (JNC) has conducted the collaboration concerning vibro-packed fuels with Paul Scherrer Institut (PSI) in Switzerland and Nuclear Research & consultancy Group (NRG) in the Netherlands. The project "Research and Development of Advanced Sphere-pac fuel" is called FUJI (FUel irradiations for JNC and PSI) Project. In this project, three types of fuels that are sphere-pac fuels, vipac fuels, and pelletized fuels will be irradiated in the High Flux Reactor (HFR) to compare the fuel performance. Based on the drawing which has been agreed among three parties, fabrication of the pin components and welding of the upper and lower connection endplugs were performed in accordance with ISO-9001 in JNC. This report describes data of fabricated pin components, results of welding qualification tests, and quality assurance of the welded components. The fabrication of pin components was successfully completed and they were delivered to PSI in October 2002.
Ishihara, Miho; Hinai, Hiroshi; Nakamura, Masahiro; Yano, Kimihiko; Nakajima, Yasuo; Washiya, Tadahiro
no journal, ,
no abstracts in English
Hinai, Hiroshi; 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. 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.
Aihara, Haruka; Hinai, Hiroshi; Nakajima, Yasuo
no journal, ,
no abstracts in English
Fukuda, Yuhei; Suganuma, Takashi; Hinai, Hiroshi; Ikeda, Akira*; Obata, Masamichi*; Shibata, Atsuhiro; Nomura, Kazunori
no journal, ,
no abstracts in English
Fukuda, Yuhei; Arai, Yoichi; Suganuma, Takashi; Hinai, Hiroshi; Sano, Yuichi; Shibata, Atsuhiro; Nomura, Kazunori
no journal, ,
no abstracts in English
Arai, Yoichi; Sano, Yuichi; Suganuma, Takashi; Hinai, Hiroshi; Ikeda, Akira*; Obata, Masamichi*; Shibata, Atsuhiro; Nomura, Kazunori
no journal, ,
no abstracts in English
Fukuda, Yuhei; Suganuma, Takashi; Hinai, Hiroshi; Ikeda, Akira*; Obata, Masamichi*; Shibata, Atsuhiro; Nomura, Kazunori
no journal, ,
no abstracts in English
Fukuda, Yuhei; Hinai, Hiroshi; Shibata, Atsuhiro; Nomura, Kazunori; Ikeda, Akira*; Obata, Masamichi*; Ichikawa, Masashi*; Takahashi, Ryota*; Hirayama, Fumio*
no journal, ,
no abstracts in English
Fukuda, Yuhei; Arai, Yoichi; Hinai, Hiroshi; Nomura, Kazunori; Ikeda, Akira*; Obata, Masamichi*; Ichikawa, Masashi*; Takahashi, Ryota*; Hirayama, Fumio*
no journal, ,
no abstracts in English
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
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.
Oki, Keiichi; Takahatake, Yoko; Hinai, Hiroshi; Shibata, Atsuhiro; Koma, Yoshikazu
no journal, ,
no abstracts in English
ray emitting nuclides at CPFMotoyama, Risa; Hinai, Hiroshi; Ichige, Yoshiaki; Shibata, Atsuhiro; Nomura, Kazunori
no journal, ,
Various properties of radioactive wastes generated at the Fukushima Daiichi Nuclear Power Station have been analyzed at Chemical Processing Facility (CPF) in Japan Atomic Energy Agency (JAEA) to contribute to their future treatment and disposal studies. The radioactive concentration of ray emitting nuclides is one of the essential information as well as those of ray and 
ray emitting nuclides. It needs to develop separation and purification methods for each -emitter from unfamiliar mediums to the nuclear fuel cycle field. Due to the restrictions of the facility, these methods should avoid using halogen reagents. The steady analysis procedures of H-3, Sr-90 and I-129 have been already developed and in practice. Among them, the analysis method of I-129 will be presented and the determination method for Se-79 will be reported as issue currently under consideration.
Hinai, Hiroshi; Nitta, Ayako; Shibata, Atsuhiro; Koma, Yoshikazu; Kaneko, Masaaki*; Ichikawa, Masashi*
no journal, ,
no abstracts in English
Ichikawa, Masashi*; Kaneko, Masaaki*; Koma, Yoshikazu; Hinai, Hiroshi; Nitta, Ayako; Shibata, Atsuhiro
no journal, ,
To study on treatment and disposal of solid waste generated at Fukushima Daiichi NPS (1F), radionuclide composition of sample taken from the bottom of primary containment vessel (PCV) of unit 1 was acquired by radioactivity analysis. It was the first time that nuclide composition data of samples taken from the inside of the reactor had been acquired, and the acquisition of these data will make it possible to estimate the origin of contaminants.
Kaneko, Masaaki*; Ichikawa, Masashi*; Hinai, Hiroshi; Nitta, Ayako; Shibata, Atsuhiro; Koma, Yoshikazu
no journal, ,
no abstracts in English
Aihara, Haruka; Hinai, Hiroshi; Kitawaki, Shinichi; Nakajima, Yasuo; Taguchi, Katsuya
no journal, ,
no abstracts in English
