3-D System-Scale Thermal-Hydraulic Code Applications in Canada

Abstract of the technical paper/presentation presented at:
Kick-Off Meeting of the Working Group on the Analysis and Management of Accidents Task Group on a State-of-the-Art Report on the Simulation Capability of 3-D System-Scale Thermal-Hydraulic Codes (3DSYSTH)
April 28–29, 2016

Prepared by:
Aleksandar Delja
Canadian Nuclear Safety Commission

Abstract:

Thermal-hydraulic modeling and simulation of transient and accident conditions in nuclear reactor installations have a significant role in reactor safety. This presentationaddresses the recent application of 3D system-scale thermal-hydraulic codes in Canada. The CANDU, as a channel type reactor, has specific areas of interest for modelling using 3D thermal-hydraulic system codes. These focus areas and expectations on capability of 3D thermal-hydraulics along withs a brief history computer code development in Canada are discussed. The presentation also includes a discussion on application of 3D thermal-hydraulic codes in Canada, particularly in independent assessments related to modelling research reactors.

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