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Your search keyword '"Nagasaka, Takuya"' showing total 21 results
Start Over Author "Nagasaka, Takuya" Journal plasma and fusion research
21 results on '"Nagasaka, Takuya"'

2. Tritium Release from Molten FLiNaBe under Low Flux Neutron Irradiation

Author

KUMAGAI, Kohki, primary, TANAKA, Teruya, additional, NAGASAKA, Takuya, additional, YAGI, Juro, additional, WATANABE, Takashi, additional, YAMAZAKI, Gaku, additional, SATO, Fuminobu, additional, TAMAKI, Shingo, additional, MURATA, Isao, additional, FUKADA, Satoshi, additional, KATAYAMA, Kazunari, additional, and SAGARA, Akio, additional

Published
2019
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3. Fabrication of the hydrogen recovery unit in the molten salt loop Oroshi2i-1 and preliminary evaluation for hydrogen transfer

Author

Nagasaka, Takuya, Tanaka, Teruya, Sagara, Akio, Muroga, Takeo, Kondo, Masatoshi, Watanabe, Takashi, Satoshi, fukada, Hiroshi, Yukawa, Nambu, Tomonori, and Iikubo, Tomohito

Subjects
molten salt, Hydrogen permeation, fusion blanket
Abstract

Hydrogen recovery unit is developed for the molten salt loop Orosh 2 i-1. Pure Ni was selected as hydrogen permeation material due to its industrial maturity of fabrication technology and goodcompatibility with molten salt in fusion reactor condition. No significant degradation of hydrogen permeabilityof the pure Ni during the fabrication process. Advanced hydrogen permeation materials, such as Pd, V, Nb, and Ta, maintaining higher hydrogen permeability are also discussed to develop more compact hydrogen recovery systems.

Published
2012

4. Corrosion behavior of hydrogen permeation materials in molten salt Flinak

Author

Nagasaka, Takuya, Kondo, Masatoshi, Sagara, Akio, and Muroga, Takeo

Subjects
molten salt, Flinak, Hydrogen permeation, forced convection loop
Abstract

Corrosion characteristics of hydrogen-permeation materials (e.g., Pd-Ag, pure V, Nb, and Ta) are examined in molten salt Flinak, in order to develop a hydrogen-recovery section for a Flinak forced convection loop “Op-erational Recovery of Separated Hydrogen and Heat Inquiry -1 (Orosh 2 i-1).” It is determined that their corrosion rate is not significant at 873 K under static conditions, compared with that of JLF-1 ferritic steel. However, pure V indicates a relatively high weight gain, likely due to O absorption. Dissolution of highly radioactive elements (e.g., Ag and Nb) is also indicated. The corrosion mechanisms and characteristics of the constituent elements are analyzed.

Published
2011

13. Manufacture of Vacuum Plasma Spraying Tungsten with Homogenous Texture on Reduced Activation Ferritic Steel at about 873 K

Author

TOKUNAGA, Tomonori, primary, WATANABE, Hideo, additional, YOSHIDA, Naoaki, additional, NAGASAKA, Takuya, additional, KASADA, Ryuta, additional, KIMURA, Akihiko, additional, TOKITANI, Masayuki, additional, MITSUHARA, Masatoshi, additional, NAKASHIMA, Hideharu, additional, MASUZAKI, Suguru, additional, TAKABATAKE, Takeshi, additional, KUROKI, Nobuyoshi, additional, EZATO, Koichiro, additional, SUZUKI, Satoshi, additional, and AKIBA, Masato, additional

Published
2013
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20. Corrosion characteristic of AlN, Y2O3, Er2O3 and Al2O3 in Flinak for molten salt blanket system

Author

Watanabe, Takashi, Kondo, Masatoshi, Nagasaka, Takuya, and Sagara, Akio

Subjects
corrosion, ceramic, Al2O3, coating, hydrogen permeation, Y2O3, Er2O3
Abstract

For liquid breeder blanket system using molten salts, tritium barrier, anti-corrosion barrier, tritium recovery system and heat exchanger make important roles. Especially in the heat exchanger, the tritium permeation from primary coolant loop to secondary coolant loop mustbe inhibited by the tritium barrier for safety. To develop it, it is essential to optimize chemical stability of the barrier material against molten salts. In the present study, the corrosion on bulk specimens of AlN, Y2O3Er2O3and Al2O3in Flinak was investigated. The static corrosion tests were performed for 230 and 1010 hours using these specimens with high purity Flinak at 600C in Ar atmosphere. Weight measurement and surface analysis of the specimens were carried out before and after the corrosion test. Chemical analysis of the Flinak also did before and after the corrosion test. AlN showed corrosion resistance, even though the surface was slightly oxidized and corroded. Er2O3, Y2O3and Al2O3dissolved into Flinak. In Er2O3corrosion, Zr in the matrix as an impurity might affect on the corrosion. The Y2O3 corrosion was small. The weight loss due to the corrosion was affected by the breaking of the specimens with porous structure. And the Al2O3corrosion was large. The surface structure changed to rough surface. These corrosion behaviors agreed withprediction based on thermodynamic evaluation.

Published
2010

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