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dc.contributor.authorMasala, Eugene
dc.contributor.authorBlomeley, Laura
dc.contributor.authorWatts, David G.
dc.contributor.authorBromley, Blair P.
dc.date.accessioned2025-04-21T10:03:50Z
dc.date.available2025-04-21T10:03:50Z
dc.date.copyright10/8/2024 12:00:00 AM
dc.date.issued2024
dc.identifier.issn2332-8983
dc.identifier.otherners_011_02_021501.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4305410
dc.description.abstractThis paper presents the findings of studies conducted at Canadian Nuclear Laboratories (CNL) to support the development of small modular reactor (SMR) designs. The primary focus of this research was to evaluate the suitability of the zero energy deuterium 2 (ZED-2) critical facility in replicating the reactor physics environment for a pressurized water reactor small modular reactor (PWR-SMR) design concept through similarity and nuclear data sensitivity studies, using the TSUNAMI code suite. It was found that previous ZED-2 experiments would be quite promising for application to a PWR-SMR design. Further similarity and sensitivity studies of hypothetical mixed-lattice substitution experiments, where PWR-SMR fuel assemblies were placed into a substitution region of the ZED-2 critical facility demonstrated improved similarity. Subsequent analyses focused on the impacts of dissolved Gadolinium (Gd) and boron (B) neutron absorbers, suggesting the feasibility of using future ZED-2 experiments to more closely replicate PWR-SMR reactor physics behavior. Building on these initial findings, the design for PWR-SMR fuel assembly substitution experiments in the ZED-2 facility were explored further. These hypothetical experiments feature water-cooled PWR-type fuel assemblies inside a shroud, surrounded by heavy-water-moderated CANdu FLEXible, Low Enriched Uranium, Recovered Uranium (CANFLEX-LEU/CANFLEX-RU) fuel channels. Similarity and sensitivity studies indicate a very high level of similarity of these experiments for PWR-SMR design applications.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleTSUNAMI Analyses of the Similarity and Applicability of Zero Energy Deuterium 2 Critical Experiments for Reactor Physics Code Benchmarking for a Pressurized Water Reactor Small Modular Reactor Design Concept
dc.typeJournal Paper
dc.journal.volume11
dc.journal.issue2
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4066404
dc.journal.fristpage21501-1
dc.journal.lastpage21501-14
dc.page14
dc.treeJournal of Nuclear Engineering and Radiation Science:;2024:;volume( 011 ):;issue: 002
dc.contenttypeFulltext


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