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Physics Modeling for Conceptual Designs of Proposed Experiments in the ZED-2 Critical Facility for Testing SMR-Type Fuels


 To assess the ability of existing nuclear facilities to model Small Modular Reactor (SMR) technology, Monte Carlo neutron transport models were conceived for the ZED-2 heavy water critical facility at the Chalk River site of Canadian Nuclear Laboratories (CNL) for a set of mixed-lattice substitution experiments using representative fuel assemblies (FAs) for Pressurized-Water Reactor (PWR), High-Temperature Gas-cooled Reactor (HTGR) and Fluoride-salt-cooled High-temperature Reactor (FHR) technologies, with driver fuel channels containing CANFLEX-LEU/RU fuel bundles. Simulation results indicate that a number of critical core configurations are possible, and should provide suitable reactor physics measurement data that can be used for physics design verification, and also for benchmarking and validation of computational reactor physics codes used in the design, operations and safety analysis of SMRs based on PWR, HTGR or FHR technologies.