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Kawamura, Yoshinori; Iwai, Yasunori; Munakata, Kenzo*; Yamanishi, Toshihiko
Journal of Nuclear Materials, 442(1-3), p.S455 - S460, 2013/11
Times Cited Count：13 Percentile：69.38(Materials Science, Multidisciplinary)Zeolite easily exchanges its cation to another. In this work, synthetic mordenite type zeolite (Na-MOR) was used as start material. And, its cation (Na
) has been exchanged by Li, K, Mg
and Ca. Then, adsorption capacities of H
and D on them were investigated at 77 K, 159 K, 175 K and 195 K. Adsorption capacities on Li-MOR and Ca-MOR became larger than that on Na-MOR at low pressure range. Oppositely, that on K-MOR became smaller. In case of alkaline metal, cation with small atomic number may lead to large adsorption capacity.
Kawamura, Yoshinori; Iwai, Yasunori; Hayashi, Takumi; Yamanishi, Toshihiko; Munakata, Kenzo*
Fusion Science and Technology, 56(1), p.168 - 172, 2009/07
Times Cited Count：5 Percentile：35.91(Nuclear Science & Technology)Synthesis zeolite is the candidate material of the separation column of the gas chromatograph for the hydrogen isotope analysis. Mordenite (MOR) is one of the zeolite, and has been reported that the MOR column can separate hydrogen isotope at about 200 K. So, the present authors have investigated the adsorption capacities of H and D on MOR at various temperatures, and have predicted the adsorption isotherms of HD, HT, DT and T. In this work, the adsorption capacities of tritium on MOR at 77 K and 87 K were investigated, and they were compared with the predicted isotherms. The observed isotherm at 87 K agreed with the predicted isotherm fairly well. However, at 77 K, the adsorption capacity at low presser region was smaller than the isotherm of D.
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.
Seki, Akiyuki; Saito, Osamu; Suzuki, Kenta; Tomishima, Katsuya; Munakata, Toshihiko; Ajima, Takumi; Saito, Kimiaki; Takemiya, Hiroshi
no journal, ,
no abstracts in English
