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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.”
Takumi Hayashi, Masayuki Yamada, Takumi Suzuki, Yuji Matsuda, Kenji Okuno
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1503-1508
Tritium Waste Management and Discharge Control | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30625
Articles are hosted by Taylor and Francis Online.
A new tritium removal system using gas separation membranes has been studied to develop more compact and cost-effective system for a fusion reactor. To obtain necessary parameters, which are directly scale able to the ITER Atmospheric Detritiation System, the basic tritium recovery performance was investigated with a scaled polyimide membrane module (hollow-filament type : 10 m3/hr ) loop. The result shows that the H2 recovery ratio from N2 or Air was more than 99 % or about 97 %, respectively, at flow rate ratio of permeated/feed =0.1, feed & permeated side pressures = 2580 & 80 torr, and module temp. = 293 K. Tritium (HT) recovery function was almost the same of H2 recovery, even though the total hydrogen concentration was a few ppm in the feed of module. H2O recovery performance was better than hydrogen recovery. These recovery functions were improved effectively decreasing the pressure ratio of permeated/feed of module.