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Yamanishi, Toshihiko; Hayashi, Takumi; Iwai, Yasunori; Isobe, Kanetsugu; Hara, Masanori*; Sugiyama, Takahiko*; Okuno, Kenji*
Fusion Engineering and Design, 86(9-11), p.2152 - 2155, 2011/10
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)It is quite significant subject how to confine the tritium in a fusion reactor. Especially, it is strongly desired to get the data for tritiated water. This is because tritiated water is much hazardous than the hydrogen form of tritium. As for the behavior of high concentration tritium water, we could get a series of valuable data for the corrosion of the tritiated water against metal materials. In the case where a metal material is in water, an oxidized layer is formed at the surface of the metal. The oxidized layer functions as a passive layer for the corrosion. However, it has been observed that the formation of the oxidized layer was prevented by the presence of tritium in water (0.23 GBq/cc). The chemical exchange column has been applied in ITER as the tritium recovery system from tritiated water. A set of data for an advanced chemical exchange column has been obtained.
Yamanishi, Toshihiko; Hayashi, Takumi; Iwai, Yasunori; Isobe, Kanetsugu; Hara, Masanori*; Sugiyama, Takahiko*; Okuno, Kenji*
Purazuma, Kaku Yugo Gakkai-Shi, 85(10), p.716 - 725, 2009/10
In a fusion reactor, tritium must be handled in a vacuum vessel, a fuel cycle, and other systems. It is quite significant subject how to confine the tritium in these systems. ITER is the first machine in the world where the tritium confinement would be demonstrated. It is essential to establish a series of database for tritium handling technology to analyze the data obtained at ITER. Especially, it is strongly desired to get the data for tritium water. This is because tritium water is much hazardous than the hydrogen form of tritium. For these reasons, our attention is focused on the study on the behavior of tritium water in the fuel cycle system and structural materials of the system. As for the behavior of high concentration tritium water, we could get the first series of valuable data for the corrosion of the tritium water against metal materials in the world. The behavior of tritium in a surface area of metal and organic compounds was also discussed. As for tritium recovery from tritium water, we could get the data on an advanced chemical exchange column. The chemical exchange column has been applied in ITER as the tritium recovery system from tritium water. Our data showed that the column performance could be remarkably improved. Tritium durability and catalyst tests have also been carried out for the chemical exchange column. Some other possible method for the tritium recovery has also been studied such as an advance adsorption method.
Yamanishi, Toshihiko; Iwai, Yasunori; Isobe, Kanetsugu; Sugiyama, Takahiko*
Purazuma, Kaku Yugo Gakkai-Shi, 83(6), p.545 - 559, 2007/06
no abstracts in English
Sugiyama, Takahiko*; Yamanishi, Toshihiko; Munakata, Kenzo*; Asakura, Yamato*; Yamamoto, Ichiro*; Glugla, M.*
no journal, ,
We report a design of the column interior which was designed to fit into the existing facility dedicated for LPCE process characterization (under the limitation of the TLK facility). The experimental conditions such as liquid and gas flow-rates, temperature have been established during preliminary investigations carried out at Nagoya University. The column to be used in the TLK facility is stainless steel tube with 55 mm internal diameter and 2 m length. The tritium separation experiments are performed at 120 kPa, 343 K. A stage-wise model was also developed to predict separative performance of the column. This model requires the channeling coefficients. The channeling coefficient which represents axial dispersion of the packed bed is evaluated against flow rates of water by impulse response. Analytical results with the present model present effects of the catalysis quantity and the gas-liquid ratio on separative performances of the column.
Yamanishi, Toshihiko; Hayashi, Takumi; Iwai, Yasunori; Isobe, Kanetsugu; Sugiyama, Takahiko*; Hara, Masanori*; Okuno, Kenji*
no journal, ,
As the activities of Grants-in-Aid for Scientific Research from MEXT, the effects of tritium water and organic tritium on the confinement materials of fusion reactors have been studied. The corrosion and permeation of tritium on the metals and organic compounds have been studied. For the tritium water processing technology, the characteristics of the chemical exchange column have been studied. These R&D studies allow us to examine the safety of fusion reactors.
