Uncertainty quantification of PWR spent fuel due to nuclear data and modeling parameters
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DOI: 10.1016/j.net.2020.07.012
Abstract: Abstract Uncertainties are calculated for pressurized water reactor (PWR) spent nuclear fuel (SNF) characteristics. The deterministic code STREAM is currently being used as an SNF analysis tool to obtain isotopic inventory, radioactivity, decay heat, neutron… read more here.
Keywords: pwr spent; modeling parameters; uncertainty; nuclear data ... See more keywords