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Collaborative Laboratories for Advanced Decommissioning Science; Osaka University*
JAEA-Review 2021-046, 77 Pages, 2022/01
The Collaborative Laboratories for Advanced Decommissioning Science (CLADS), Japan Atomic Energy Agency (JAEA), had been conducting the Nuclear Energy Science & Technology and Human Resource Development Project (hereafter referred to "the Project") in FY2020. The Project aims to contribute to solving problems in the nuclear energy field represented by the decommissioning of the Fukushima Daiichi Nuclear Power Station, Tokyo Electric Power Company Holdings, Inc. (TEPCO). For this purpose, intelligence was collected from all over the world, and basic research and human resource development were promoted by closely integrating/collaborating knowledge and experiences in various fields beyond the barrier of conventional organizations and research fields. The sponsor of the Project was moved from the Ministry of Education, Culture, Sports, Science and Technology to JAEA since the newly adopted proposals in FY2018. On this occasion, JAEA constructed a new research system where JAEA-academia collaboration is reinforced and medium-to-long term research/development and human resource development contributing to the decommissioning are stably and consecutively implemented. Among the adopted proposals in FY2018, this report summarizes the research results of the "Development of technology to simultaneously measure viscosity and surface tension of molten materials in reactor core" conducted from FY2018 to FY2020. Since the final year of this proposal was FY2020, the results for three fiscal years were summarized. Since (U, Zr)O and boride, molten materials in reactor core, exist at extremely high temperature, chemical reactions between the vessel and these molten materials are unavoidable. Therefore, it is difficult to measure the thermophysical property of these materials. In the present study, droplets are produced by heating and melting the samples levitated by a gas levitation method, then the droplets are collided with a substrate.
Myagmarjav, O.; Shibata, Ai*; Tanaka, Nobuyuki; Noguchi, Hiroki; Kubo, Shinji; Nomura, Mikihiro*; Takegami, Hiroaki
International Journal of Hydrogen Energy, 46(56), p.28435 - 28449, 2021/08
Times Cited Count:3 Percentile:10.63(Chemistry, Physical)Segawa, Tomoomi; Kawaguchi, Koichi; Ishii, Katsunori; Suzuki, Masahiro; Tachihara, Joji; Takato, Kiyoto; Okita, Takatoshi; Satone, Hiroshi*; Suzuki, Michitaka*
Mechanical Engineering Journal (Internet), 8(3), p.21-00022_1 - 21-00022_9, 2021/06
To reduce the hold-up of the nuclear fuel materials in the glove box and the external exposure dose, the technology of the MOX powder adhesion prevention by the nanoparticle coating to the acrylic panels of the glove box has been developed. The surface analysis by means of atomic force microscopy (AFM) showed that the acrylic test piece surface coated with nanoparticles had a higher root mean square roughness value than that non-coated with nanoparticles. Due to the formation of nano-sized tiny rugged surface, the nanoparticle coating reduced the minimum adhesion force between the UO particles and the acrylic test piece surface with the smallest particle size of about 5
m where desorption was observed, by about one-tenth. Moreover, the nanoparticle coating reduced the amount of the MOX powder adhering to the acrylic test piece to about one-tenth. In this study, it was found that applying the nanoparticle coating to the acrylic panels of glove box can prevent the adhesion of nuclear fuel materials. This method is effective for reducing the hold-up of the nuclear fuel materials in the glove box, the external exposure dose and improving the visibility of the acrylic panels.
Collaborative Laboratories for Advanced Decommissioning Science; Osaka University*
JAEA-Review 2020-038, 41 Pages, 2020/12
JAEA/CLADS had been conducting the Nuclear Energy Science & Technology and Human Resource Development Project in FY2019. Among the adopted proposals in FY2018, this report summarizes the research results of the "Development of Technology to Simultaneously Measure Viscosity and Surface Tension of Molten Materials in Reactor Core" conducted in FY2019.
Furutani, Misa; Kometani, Tatsunari; Nakagawa, Masahiro; Ueno, Yumi; Sato, Junya; Iwai, Yasunori*
Hoken Butsuri (Internet), 55(2), p.97 - 101, 2020/06
Herein, an oxidation catalyst was introduced after heating it to 600C to oxidize tritium gas (HT) existing in exhaust into tritiated water vapor (HTO). This study aims to establish a safer
H monitoring system by lowering the heating temperature required for the catalyst. In these experiments, which were conducted in the Nuclear Science Research Institute, Japan Atomic Energy Agency, cupric oxide, hydrophobic palladium/silicon dioxide (Pd/SiO
), and platinum/aluminum oxide (Pt/Al
O
) catalysts were ventilated using standard hydrogen gas. After comparing the oxidation efficiency of each catalyst at different temperatures, we found that the hydrophobic Pd/SiO
and Pt/Al
O
catalysts could oxidize HT into HTO at 25
C.
Collaborative Laboratories for Advanced Decommissioning Science; Osaka University*
JAEA-Review 2019-025, 36 Pages, 2020/01
CLADS, JAEA, had been conducting the Center of World Intelligence Project for Nuclear Science/Technology and Human Resource Development (hereafter referred to "the Project") in FY2018. The Project aims to contribute to solving problems in nuclear energy field represented by the decommissioning of the Fukushima Daiichi Nuclear Power Station, Tokyo Electric Power Company Holdings, Inc. For this purpose, intelligence was collected from all over the world, and basic research and human resource development were promoted by closely integrating/collaborating knowledge and experiences in various fields beyond the barrier of conventional organizations and research fields. The sponsor of the Project was moved from the Ministry of Education, Culture, Sports, Science and Technology to JAEA since the newly adopted proposals in FY2018. On this occasion, JAEA constructed a new research system where JAEA-academia collaboration is reinforced and medium-to-long term research/development and human resource development contributing to the decommissioning are stably and consecutively implemented. Among the adopted proposals in FY2018, this report summarizes the research results of the "Development of Technology to Simultaneously Measure Viscosity and Surface Tension of Molten Materials in Reactor Core". Since (U,Zr)O and boride, molten materials in reactor core, exist at extremely high temperature, chemical reactions between the vessel and these molten materials are unavoidable. Therefore, it is difficult to measure the thermophysical property of these materials. In the present study, droplets are produced by heating and melting the samples levitated by a gas levitation method, then the droplets are collided with a substrate. From the instant behavior of the collision, a new technology to simultaneously derive the viscosity and surface tension will be developed.
Ueno, Yumi; Nakagawa, Masahiro; Sato, Junya; Iwai, Yasunori
Hoken Butsuri, 51(1), p.7 - 11, 2016/03
In the Nuclear Science Research Institute, Japan Atomic Energy Agency (JAEA), in order to oxidize C, which exists in various chemical forms in exhaust, into
CO
, a copper oxide (CuO) catalyst is introduced after heating to 600
C. Our goal was to establish a safer
C monitoring system by lowering the heating temperature required for the catalyst; therefore, we developed a new hydrophobic palladium/silicon dioxide (Pd/SiO
) catalyst that makes the carrier's surface hydrophobic. In these experiments, catalysts CuO, platinum/aluminum oxide (Pt/Al
O
), palladium/zirconium dioxide (Pd/ZrO
), hydrophobic Pd/SiO
, and hydrophilic Pd/SiO
were ventilated with standard methane gas, and we compared the oxidation efficiency of each catalyst at different temperatures. As a result, we determined that the hydrophobic Pd/SiO
catalyst had the best oxidation efficiency. By substituting the currently used CuO catalyst with the hydrophobic Pd/SiO
catalyst, we will be able to lower the working temperature from 600
C to 300
C and improve the safety of the monitoring process.
Ishiyama, Shintaro
Nihon Kinzoku Gakkai-Shi, 68(6), p.353 - 361, 2004/06
Times Cited Count:0 Percentile:0.00(Metallurgy & Metallurgical Engineering)AlO
and ZrO
coating test was performed on the surface of Ni based super alloy by ion plateing technique and high density and homegeneity ceramic thin coating with the thichkness of 4
m was formed on the specimen surface. 1173K-RT heat cycle and FP plat-out tests were performed with these coate specimens and no damage was found under 100 cycles and there is no plate-out onto the these specimens.
Nakamichi, Masaru; Kawamura, Hiroshi
Fusion Engineering and Design, 58-59, p.719 - 723, 2001/11
Times Cited Count:13 Percentile:66.47(Nuclear Science & Technology)no abstracts in English
Isobe, Motoyasu; Kameo, Yutaka; Nakashio, Nobuyuki; Wakui, Takuji*; Iwata, Keiji*; Kibayashi, Tatsuyuki*; Kanazawa, Katsuo; Nakashima, Mikio; Hirabayashi, Takakuni*
JAERI-Tech 2000-049, 29 Pages, 2000/09
no abstracts in English
Katano, Yoshio*; Aruga, Takeo; Yamamoto, Shunya; Nakazawa, Tetsuya; Yamaki, Daiju
Proceedings of 2000 International Conference on Ion Implantation Technology (IIT 2000), p.805 - 808, 2000/00
no abstracts in English
Yamada, Reiji; Snead, L. L.*; Kato, Yudai*
Proceedings of 4th International Energy Agency Workshop on SiCf/SiC Ceramic Composites for Fusion Structural Application, p.175 - 180, 2000/00
no abstracts in English
Hidaka, Akihide; Maruyama, Yu; Ueno, Shingo*; Sugimoto, Jun
JAERI-Conf 99-005, p.49 - 55, 1999/07
no abstracts in English
Dai, Z.*; P.Zhu*; Yamamoto, Shunya; Miyashita, Atsumi; Narumi, Kazumasa; Naramoto, Hiroshi
Thin Solid Films, 339(1-2), p.114 - 116, 1999/00
Times Cited Count:29 Percentile:78.79(Materials Science, Multidisciplinary)no abstracts in English
Tanifuji, Takaaki; Katano, Yoshio; ; Noda, Kenji
Journal of Nuclear Materials, 253, p.156 - 166, 1998/00
Times Cited Count:5 Percentile:43.97(Materials Science, Multidisciplinary)no abstracts in English
; ; Araki, Masanori; Nakamura, Kazuyuki; Akiba, Masato
Journal of Nuclear Materials, 258-263, p.318 - 322, 1998/00
Times Cited Count:8 Percentile:56.81(Materials Science, Multidisciplinary)no abstracts in English
; ; Nakamura, Kazuyuki; Akiba, Masato
Proceedings of 17th IEEE/NPSS Symposium Fusion Engineering (SOFE'97), 1, p.385 - 388, 1998/00
no abstracts in English
Sugimoto, Makoto; Takano, Katsutoshi*; Tsuji, Hiroshi; Abe, Kazuhiko*; ;
Teion Kogaku, 33(11), p.716 - 723, 1998/00
no abstracts in English
Naramoto, Hiroshi; Aoki, Yasushi; Yamamoto, Shunya; Abe, Hiroaki
Nuclear Instruments and Methods in Physics Research B, 127-128, p.599 - 602, 1997/00
Times Cited Count:12 Percentile:67.48(Instruments & Instrumentation)no abstracts in English
Onozuka, Masanori*; Tsujimura, Seiji*; Toyoda, Masahiko*; Inoue, Masahiko*; Abe, Tetsuya; Murakami, Yoshio
Fusion Technology, 29(1), p.73 - 82, 1996/01
Times Cited Count:9 Percentile:61.58(Nuclear Science & Technology)no abstracts in English