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steam-generating heavy-water reactor

noun

  1. a nuclear reactor using heavy water as the moderator, light water (H 2 O) as the coolant, and uranium oxide cased in zirconium alloy as the fuel SGHWR
“Collins English Dictionary — Complete & Unabridged” 2012 Digital Edition © William Collins Sons & Co. Ltd. 1979, 1986 © HarperCollins Publishers 1998, 2000, 2003, 2005, 2006, 2007, 2009, 2012


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