TITLE

Next-Generation CANDU Technology

AUTHOR(S)
Hopwood, Jerry; Hedges, Kenneth; Pakan, Mark
PUB. DATE
September 2002
SOURCE
Nuclear Plant Journal;Sep/Oct2002, Vol. 20 Issue 5, p35
SOURCE TYPE
Trade Publication
DOC. TYPE
Article
ABSTRACT
This paper was presented earlier this year at the Tenth International Conference On Nuclear Engineering (ICONE-10). It summarizes the main features and characteristics of the ACR-700™, the reference design for Atomic Energy of Canada Limited's (AECL) next-generation Advanced CANDU Reactor™. The plant design is based on the adaptation of existing CANDU® components. It uses slightly enriched uranium fuel, the existing CANDU fuel channel module, along with light water coolant and a heavy water moderator and reflector.
ACCESSION #
9034930

 

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