Applicability of Canadian Seismic Design Codes to Small Modular Reactors (SMRs)
Main Article Content
Abstract
A review of the nuclear CSA codes addressing seismic design (CSA N289) considering SMR-specific features that might be different from those of existing water-cooled reactors has been performed. Gaps in the reviewed codes pertaining to seismic design and analysis of SMRs are identified. A graded scheme is applied in the code review and in identification of gaps. Proposals to address the identified gaps are presented.
Article Details
Section
Articles