Uncertainty quantifi cation in decay heat calculation of spent nuclear fuel by STREAM/RAST-K

• Published in: Nuclear engineering and technology 2021, 53(9), , pp.2803-2815
• Main Authors: 장재림, 공치동, Bamidele Ebiwonjumi, Alexey Cherezov(UNIST, 조윤기, 이덕중
• Format: Article
• Language: English
• Subjects: 원자력공학
• ISSN: 1738-5733; 2234-358X
• DOI: 10.1016/j.net.2021.03.010

This paper addresses the uncertainty quantification and sensitivity analysis of a depleted light-water fuelassembly of the Turkey Point-3 benchmark. The uncertainty of the fuel assembly decay heat and isotopicdensities is quantified with respect to three different groups of diverse parameters: nuclear data, assembly design, and reactor core operation. The uncertainty propagation is conducted using a two-stepanalysis code system comprising the lattice code STREAM, nodal code RAST-K, and spent nuclear fuelmodule SNF through the random sampling of microscopic cross-sections, fuel rod sizes, number densities, reactor core total power, and temperature distributions. Overall, the statistical analysis of thecalculated samples demonstrates that the decay heat uncertainty decreases with the cooling time. Thenuclear data and assembly design parameters are proven to be the largest contributors to the decay heatuncertainty, whereas the reactor core power and inlet coolant temperature have a minor effect. Themajority of the decay heat uncertainties are delivered by a small number of isotopes such as 241Am, 137Ba, 244Cm, 238Pu, and 90Y. © 2021 Korean Nucl KCI Citation Count: 0