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Sekine, Yurina; Nankawa, Takuya; Yamada, Teppei*; Matsumura, Daiju; Nemoto, Yoshihiro*; Takeguchi, Masaki*; Sugita, Tsuyoshi; Shimoyama, Iwao; Kozai, Naofumi; Morooka, Satoshi
Journal of Environmental Chemical Engineering, 9(2), p.105114_1 - 105114_12, 2021/04
Times Cited Count：0 Percentile：0(Engineering, Environmental)Remediating toxic ion contamination is crucial for protecting human health and the environment. This study aimed to provide a powerful strategy for effectively utilizing bone waste from the food production and preparation industries for removal of toxic ions. Here, we show that immersing pig bone in NaHCO
solution produced a carbonated nanohydroxyapatites (C-NHAP). The C-NHAP exhibited high adsorptivity for Sr
, Cd, Pb, and Cu. The strontium adsorptivity was about 250 and 4,500 times higher than that of normal bone and synthetic HAP, respectively. The C-NHAP is an eco-friendly, high-performance material that is simple to prepare and should be useful for tackling problems of food waste disposal and environmental pollution.
Suzuki, Hiroaki*; Morita, Yoshihiro*; Naito, Masanori*; Nemoto, Yoshiyuki; Kaji, Yoshiyuki
Mechanical Engineering Journal (Internet), 7(3), p.19-00450_1 - 19-00450_17, 2020/06
In this study, the SAMPSON code was modified to evaluate severe accidents in a spent fuel pool (SFP). Air oxidation models based on oxidation data obtained on the Zircaroy-4 cladding (ANL model) and the Zircaroy-2 cladding (JAEA model) were included in the modified SAMPSON code. Experiments done by Sandia National Laboratory using simulated fuel assemblies equivalent to those of an actual BWR plant were analyzed by the modified SAMPSON code to confirm the functions for analysis of the severe SFP accidents. The rapid fuel rod temperature rise due to the Zr air oxidation reaction could be reasonably evaluated by the SAMPSON analysis. The SFP accident analyses were conducted with different initial water levels which were no water, water level at bottom of active fuel, and water level at half of active fuel. The present analysis showed that the earliest temperature rise of the fuel rod surface occurred when there was no water in the SFP and natural circulation of air became possible.
Morita, Yoshihiro*; Suzuki, Hiroaki*; Naito, Masanori*; Nemoto, Yoshiyuki; Kaji, Yoshiyuki
Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 9 Pages, 2019/05
In this study, the SAMPSON code was modified to evaluate severe accidents in a spent fuel pool (SFP). Not only the SFP but also upper spaces of the SFP, walls of the reactor building, and the blowout panel were included. Air oxidation models obtained by the Zircaroy-4 cladding (ANL model) and the Zircaroy-2 cladding (JAEA model) were included in the modified SAMPSON code. Experiments done by Sandia National Laboratory using simulated fuel assemblies equivalent to those of an actual BWR plant were analyzed by the modified SAMPSON code to confirm the functions for analysis of the severe SFP accidents.
Suzuki, Hiroaki*; Morita, Yoshihiro*; Naito, Masanori*; Nemoto, Yoshiyuki; Nagatake, Taku; Kaji, Yoshiyuki
Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 7 Pages, 2019/05
In this paper, modification of the SAMPSON code was carried out to enable the analysis of spray cooling. The SAMPSON analysis of a spray cooling experiment was performed to confirm reproducibility of spray cooling behavior of fuel claddings. The modified SAMPSON code was applied to a hypothetical loss-of-coolant accident analysis of the SFP. Effectiveness of spray cooling on cladding temperature behavior was investigated. The SAMPSON analysis showed that spraying from the top of the SFP was effective for cooling the fuel assemblies exposed to the gas phase.
Tajima, Yoshihiro; Kuwabara, Jun; Oyokawa, Atsushi; Kabuto, Shoji; Araya, Naoyuki; Kikuchi, Kaoru; Miyamoto, Shingo; Nemoto, Hideyuki; Oe, Osamu
JAEA-Review 2016-003, 56 Pages, 2016/05
JAEA-Review-2016-003.pdf:7.16MB
Nuclear Facilities Management Section implements the operation, maintenance and decommissioning of the first nuclear ship "MUTSU" and the operation and maintenance of the liquid waste facility and the solid waste facility where a small amount of nuclear fuel is used. This is the report on the operations of the Nuclear Facilities Management Section for FY 2012 and FY 2013.
-ray and carbon ion beams in grain amaranthNemoto, Kazuhiro*; Tsurukawa, Akiko*; Minami, Mineo*; Matsushima, Kenichi*; Hase, Yoshihiro
JAEA-Review 2014-050, JAEA Takasaki Annual Report 2013, P. 112, 2015/03
no abstracts in English
Tobita, Kenji; Kusama, Yoshinori; Nakamura, Hiroo; Ito, Takao; Tsukahara, Yoshimitsu; Nemoto, Masahiro; Kubo, Hirotaka; Takeuchi, Hiroshi; Kuriyama, Masaaki; Matsuoka, Mamoru; et al.
Nuclear Fusion, 31(5), p.956 - 960, 1991/00
Times Cited Count：6 Percentile：36.19(Physics, Fluids & Plasmas)no abstracts in English
Tobita, Kenji; Ito, Takao; Sakasai, Akira; Kusama, Yoshinori; Ohara, Yoshihiro; Tsukahara, Yoshimitsu; Nemoto, Masahiro; Kawano, Yasunori; Kubo, Hirotaka; Takeuchi, Hiroshi; et al.
Plasma Physics and Controlled Fusion, 32(6), p.429 - 441, 1990/00
Times Cited Count：13 Percentile：46.53(Physics, Fluids & Plasmas)no abstracts in English
Tobita, Kenji; Kusama, Yoshinori; Nemoto, Masahiro; Takeuchi, Hiroshi; Ito, Takao; Tsukahara, Yoshimitsu; Shitomi, Morimasa; Watanabe, Kazuhiro; Ohara, Yoshihiro
Kaku Yugo Kenkyu, 59(SPECIAL ISSUE), p.139 - 156, 1988/00
no abstracts in English
Fukushima, Masahiro; Okajima, Shigeaki; Kitamura, Yasunori; Ando, Masaki; Yamane, Tsuyoshi; Mori, Takamasa; Nishi, Hiroshi; Yamane, Yoshihiro*; Kanemoto, Shigeru*
no journal, ,
no abstracts in English
Okajima, Shigeaki; Nishi, Hiroshi; Yamane, Yoshihiro*; Kanemoto, Shigeru*; Yamane, Tsuyoshi; Mori, Takamasa; Kitamura, Yasunori; Fukushima, Masahiro; Kitano, Akihiro; Ando, Masaki; et al.
no journal, ,
The program was planned and has been carried out to develop of the reactivity feedback effect measurement techniques under sub-critical condition in the start-up experiment for fast reactors. The program includes the demonstration of the developed technique in fast critical assembly (FCA) and the proposal of the appropriate measurement system based on the results. The background and the purposes of the program and the outline of development subjects are presented.
Okajima, Shigeaki; Nishi, Hiroshi; Kanemoto, Shigeru*; Yamane, Yoshihiro*; Fukushima, Masahiro; Kitamura, Yasunori; Kitano, Akihiro; Suzuki, Takayuki; Ando, Masaki; Yamane, Tsuyoshi
no journal, ,
no abstracts in English
Nemoto, Kazuhiro*; Minami, Mineo*; Matsushima, Kenichi*; Tsurukawa, Akiko*; Kinoshita, Junichi*; Hase, Yoshihiro
no journal, ,
no abstracts in English
Morita, Yoshihiro*; Suzuki, Hiroaki*; Naito, Masanori*; Kaji, Yoshiyuki; Nemoto, Yoshiyuki
no journal, ,
We conducted the preliminary analysis for the phenomenon of loss of coolant in Spent Fuel Pool by MAAP code and reported the analytical results for temperature and relocation behavior of spent fuel channels.
Morita, Yoshihiro*; Suzuki, Hiroaki*; Naito, Masanori*; Nemoto, Yoshiyuki; Kaji, Yoshiyuki
no journal, ,
A new model including the spent fuel pool (SFP) or Zr oxidation behavior which is necessary to evaluate the SFP accident caused by cooling function loss was developed and implanted in the severe accident code SAMPSON in this work. Results of the evaluation using the improved code will be presented.
Suzuki, Hiroaki*; Morita, Yoshihiro*; Naito, Masanori*; Kaji, Yoshiyuki; Nemoto, Yoshiyuki
no journal, ,
Severe accident code SAMPSON was upgraded by introducing the models of Zr oxidation in air, and spray cooling, etc, in this study. Analytical results on spent fuel pool (SFP) accident were obtained and effectiveness of the spray cooling system for the safety measure of the SFP was discussed in this study.
