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- W2391667578 abstract "The purpose of this calculation is to estimate the thermal response of a repository-emplaced waste package and its corresponding drift wall surface temperature with different drift diameters. The case examined is that of a 21 pressurized water reactor (PWR) uncanistered fuel (UCF) waste package loaded with design basis spent nuclear fuel assemblies. This calculation evaluates a 3.5 meter to 6.5 meter drift diameter range in increments of 1.0 meters. The time-dependent temperatures of interest, as determined by this calculation, are the spent nuclear fuel cladding temperature, the waste package surface temperature, and the drift wall surface temperature." @default.
- W2391667578 created "2016-06-24" @default.
- W2391667578 creator A5034324091 @default.
- W2391667578 date "1999-01-04" @default.
- W2391667578 modified "2023-10-18" @default.
- W2391667578 title "THERMAL EVALUATION OF DIFFERENT DRIFT DIAMETER SIZES" @default.
- W2391667578 doi "https://doi.org/10.2172/862267" @default.
- W2391667578 hasPublicationYear "1999" @default.
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