ANALYSING SUPERCRITICAL WATER REACTOR’S (SCWR’S) SPECIAL SAFETY SYSTEMS USING PROBABILISTIC TOOLS
The 5th International Symposium on SuperCritical Water-cooled Reactors - 2011 March 13-16


Presented at:
The 5th International Symposium on SuperCritical Water-cooled Reactors
2011 March 13-16
Location:
Vancouver,Canada
Session Title:
Safety Analysis

Authors:
Ima Ituen (McMaster University)
David Novog (McMaster University)
  

Abstract

The next generation of reactors, termed Generation IV, has very attractive features – its superior safety characteristics, high thermal efficiency, and fuel cycle sustainability. A key element of the Generation IV designs is the improvement in safety, which in turn requires improvements in safety system performance and reliability, as well as a reduction in initiating event frequencies. This study compares the response of the systems important to safety in the CANDU-Supercritical Water Reactor to those of the generic CANDU under a main steamline break accident and loss of forced circulation events – to quantify the improvements in safety for the pre-conceptual CANDU SCWR design. Probabilistic safety analysis is the tool used in this study to test the behavior of the pre- conceptual design during these events.

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