Code Simulation of a Preliminary Passive Moderator Cooling System for Canadian SCWR Conceptual Design
CNS 24th Nuclear Simulation Symposium - 2012 October 15-16


Presented at:
CNS 24th Nuclear Simulation Symposium
2012 October 15-16
Location:
Ottawa,Canada
Session Title:
Technical 7: Thermalhydraulics & Safety

Authors:
Sun-Kyu Yang (Atomic Energy of Canada Limited)
  

Abstract

A Passive Moderator Cooling System for the  Canadian SCWR (supercritical water-cooled reactor), using a flashing-driven natural circulation loop, is  being developed at AECL.  A preliminary conceptual design of the passive moderator cooling system for normal operation was simulated using the CATHENA code.  Major dimensions for the conceptual design of passive moderator cooling system were established.  An operation map was constructed for the established dimensions to determine the operation power range of the conceptual design of passive moderator cooling system. 

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