Uncertainty quantification of PWR spent fuel due to nuclear data and modeling parameters

Uncertainty quantification of PWR spent fuel due to nuclear data and modeling parameters

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 and gamma source strengths. The SNF analysis capab...

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Bibliographic Details
Main Authors: Bamidele Ebiwonjumi, Chidong Kong, Peng Zhang, Alexey Cherezov, Deokjung Lee
Format: Article
Language:English
Published: Elsevier 2021-03-01
Series:Nuclear Engineering and Technology
Subjects:
STREAM
Spent nuclear fuel
PWR
Uncertainty quantification
Stochastic sampling
Surrogate models
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573320303521

Internet

http://www.sciencedirect.com/science/article/pii/S1738573320303521

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