Article ID Journal Published Year Pages File Type
1567459 Journal of Nuclear Materials 2010 6 Pages PDF
Abstract
High temperature thermal property data for structural materials used in existing Light Water Reactors (LWRs) are limited. Often, values extrapolated from available data, as recommended in the literature, differ significantly. To reduce uncertainties in predictions relying upon extrapolated data for LWR vessel and penetration materials, high temperature tests were completed on SA533 Grade B, Class 1 (SA533-B1) low alloy steel, Stainless Steel 304 (SS304), and Inconel 600 using material property measurement systems available in the High Temperature Test Laboratory (HTTL) at the Idaho National Laboratory (INL). Properties measured include thermal expansion, specific heat capacity, and thermal diffusivity for temperatures up to 1200 °C. From these results, thermal conductivity and density were calculated. Results show that, in some cases, previously recommended values for these materials differ significantly from measured values at high temperatures.
Related Topics
Physical Sciences and Engineering Energy Nuclear Energy and Engineering
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