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North American construction is back—smaller and faster—at OPG’s Darlington
“The nuclear renaissance is real here,” said Ontario Power Generation’s Subo Sinnathamby on May 8, one year to the day after OPG secured a final investment decision to build the first of four planned BWRX-300 reactors at its Darlington nuclear power plant, and shortly after the new reactor’s foundation was lifted into place. “We got our license to construct in April and our [final investment decision] in May, and we’ve been off to the races since.”
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.