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Fusion Science and Technology
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New X-ray imaging for ITER-supporting tokamaks
As researchers continue to seek ways to better understand the plasma inside fusion machines to fully harness fusion energy, Princeton Plasma Physics Laboratory is leading a project to provide new X-ray imaging systems to two international tokamak projects: WEST, in southern France, and JT-60SA, in Japan—both of which are designed to support the development of ITER.
T. Kakuta, S. Konishi, Y. Kawamura, M. Nishi, T. Suzuki
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 1083-1087
Tritium | doi.org/10.13182/FST01-A11963388
Articles are hosted by Taylor and Francis Online.
Electrochemical properties of the ceramic protonic conductor cell were investigated to evaluate its feasibility of hydrogen pumping for the purpose of tritium extraction in fusion fuel system. Experiments were performed at 873~1073K. One side of the cell was exposed to pure hydrogen and the other was exposed to 0.01~10 vol. % of hydrogen balanced with helium. Static and dynamic hydrogen pumping properties of the cell were evaluated. Electromotive force generated between two electrodes by the difference of hydrogen concentration was measured as static characteristics. In the region of the ratio of hydrogen partial pressure up to 100, the electrochemical potential driven by the difference of hydrogen partial pressure agreed well with the theoretical values derived from Nemst's law. The hydrogen pumping capacity was measured as the current density with applied DC. Hydrogen was selectively transferred at the current density of 7mA/cm2 at 873K and 9mA/cm2 at 973K, which satisfy our projected requirement (above 5mA/cm2) for applying to the blanket tritium recovery system. Voltage-induced degradation of the cell material accompanied with water vapor generation was observed, and voltage region to avoid this degradation was identified.