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Kawamura, Yoshinori; Konishi, Satoshi; Nishi, Masataka
Fusion Science and Technology, 45(1), p.33 - 40, 2004/01
Times Cited Count：25 Percentile：81.9(Nuclear Science & Technology)Aiming at realization of the efficient blanket tritium recovery system of a fusion reactor, research and development of the hydrogen pump using the proton conductor are furthered. One of the advantages of the system using the hydrogen pump is concurrent processing of hydrogen isotopes and water vapor by one component. In this work, experimental research on the hydrogen extraction characteristic in a water molecule was performed with the hydrogen pump using SrCe
Yb
O
. In hydrogen extraction from a water molecule, application of the threshold, voltage corresponding to the decomposition energy of water, is necessary. The observed threshold was about 500-600mV at 873K and decreased with the increase in water vapor pressure. About pumping of H
-HO mixture gas, the permeation of H anteceded water decomposition, and the threshold of water decomposition increased with the increase in hydrogen partial pressure. In order to process concurrently, application of fairly higher voltage is expected to be necessary.
Kawamura, Yoshinori; Konishi, Satoshi; Nishi, Masataka; Kakuta, Toshiya*
Fusion Science and Technology, 41(3), p.1035 - 1039, 2002/05
To establish the nuclear fusion reactor, tritium bred in the breeder blanket of the fusion reactor must be recovered effectively. The present authors have proposed the blanket tritium recovery system using the hydrogen pump with solid electrolyte membrane. Hydrogen isotopes including tritium can be separated from helium purge gas of the breeder blanket by the protonic conductor membrane which pumps out hydrogen isotopes selectively by applying a few potential difference between its faces. Perovskite-type ceramic such as SrCeYbO
, is one of the candidate protonic conductor for hydrogen pump and its ionic hydrogen transportation properties have been investigated. Deuterium transportation properties have also been investigated to understand the isotope effect. Through the investigation up to now, the basic hydrogen isotope transportation property of SrCeYbO, its technical feasibility, and issues for further development toward the practical devices were revealed.
Kakuta, Toshiya*; Hirata, Shingo*; Mori, Seiji*; Konishi, Satoshi; Kawamura, Yoshinori; Nishi, Masataka; Ohara, Yoshihiro
Fusion Science and Technology, 41(3), p.1069 - 1073, 2002/05
Research-and-development of the supercritical water-cooled prototype fusion reactor which has cost competitiveness has been performed in Japan Atomic Energy Research Institute (JAERI). It is necessary to establish immediately the design concept of the blanket tritium recovery system which collects tritium continuously and safely from the supercritical water-cooled blanket because fuel self-sufficiency is inevitable in the prototype reactor. The candidate systems are; 1) batch-processing cryogenic molecular sheave bed recovery system with cryogenic temperature operation, 2) continuous processing Pd membrane penetration recovery system with high vacuum operation. In the present study, however, the third candidate system, the hydrogen pump system with protonic conductors, was investigated. As a result of the study, it was made clear that the system with minimized energy consumption and minimized accidental tritium release could be realized by using the hydrogen pump for the blanket tritium recovery system of the prototype fusion reactor.
Kato, Mineo; Ito, Takeshi*; Sugai, Hiroyuki; Kawamura, Yoshinori; Hayashi, Takumi; Nishi, Masataka; Tanase, Masakazu; Matsuzaki, Teiichiro*; Ishida, Katsuhiko*; Nagamine, Kanetada*
Fusion Science and Technology, 41(3), p.859 - 862, 2002/05
JAERI has a plane to develop a compact tritium gas recycling system for fusion research. This system is also very attractive for the muon-catalyzed fusion (
CF) research at RIKEN-RAL Muon Facility in UK. For the research, JAERI has produced high purity tritium gas of 1,500 Ci and transported it to the Facility. In the CF experiments, the tritium gas was diluted by the deuterium in an optional concentration and the used tritium gas was carried back by the tritium transport container developed to JAERI. If it is possible to recycle the diluted tritium gas, i.e., the used tritium gas is enriched in the experimental site, the CF experiments should be conducted efficiently. rom the above point of view, in this paper, we propose the compact tritium gas recycling system based on the gas chromatography that has already developed in JAERI and a proton conductor.
Kakuta, Toshiya*; Konishi, Satoshi; Kawamura, Yoshinori; Nishi, Masataka; Suzuki, T.*
Fusion Technology, 39(2-Part2), p.1083 - 1087, 2001/03
no abstracts in English
