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dc.contributor.authorMendoza España, Alberto D'Ansi
dc.date.accessioned2024-12-24T19:15:44Z
dc.date.available2024-12-24T19:15:44Z
dc.date.copyright5/10/2024 12:00:00 AM
dc.date.issued2024
dc.identifier.issn2332-8983
dc.identifier.otherners_010_04_040801.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4303607
dc.description.abstractCanadian Nuclear Laboratories (CNL) is collaborating in the Joint European Canadian Chinese Development of Small Modular Reactor Technology (ECC-SMART) project to understand the corrosion behavior of the most promising candidate materials for a future supercritical water-cooled – small modular reactor (SCW-SMR). To support this aim and the project's requirements, the present study develops a costing method for assessing the impact of corrosion in a power generation cost model. This cost model builds on a methodological study of various corrosion engineering economics topics in nuclear power generation, such as the expected fuel cladding corrosion phenomena in a supercritical water-cooled reactor (SCWR) concept and estimating the main corrosion costs categories. This understanding is incorporated in a power generation cost model that applies the revenue requirements approach to life cycle costing (LCC). The LCC includes the main corrosion cost categories and a reliability factor used in assessing power generation costs, the costing of chemical species for controlling corrosion, and the present worth of revenue requirements. The method and model, therefore, provide a framework for understanding the kind of information available and needed for taking economical preventative corrosion measures for the current generation of water-cooled reactors and advanced reactors, such as the SCWR.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleRevenue Requirements Method for Assessing the Cost Impact of Fuel Cladding Corrosion in a Supercritical Water-Cooled Small Modular Reactor: A Methodological Review on Life Cycle Costing Corrosion
dc.typeJournal Paper
dc.journal.volume10
dc.journal.issue4
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4064639
dc.journal.fristpage40801-1
dc.journal.lastpage40801-15
dc.page15
dc.treeJournal of Nuclear Engineering and Radiation Science:;2024:;volume( 010 ):;issue: 004
dc.contenttypeFulltext


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