THERMAL EVALUATION OF DIFFERENT DRIFT DIAMETER SIZES | Zendy

H.M. Wade | Zendy

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THERMAL EVALUATION OF DIFFERENT DRIFT DIAMETER SIZES

Author(s) -

H.M. Wade

Publication year - 1999

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/862267

Subject(s) - cladding (metalworking) , nuclear engineering , metre , thermal , radioactive waste , environmental science , nuclear fuel , materials science , range (aeronautics) , waste management , meteorology , engineering , composite material , physics , astronomy

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

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