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Nuclear Engineering Thermal-HydraulicsNuclear reactor physics and engineeringNuclear Materials and Properties

Data-driven bubble transport prediction and uncertainty quantification in lead-cooled fast reactor based on attentional feature fusion

Longcong Wang, K. Dong, Jiyun Zhao

2026.5.27ENGINEERING APPLICATIONS OF ARTIFICIAL INTELLIGENCE

DOI: 10.1016/j.engappai.2026.115023

Abstract

Abstract is not available.

Citation format

WANG, Longcong; DONG, K.; ZHAO, Jiyun. Data-driven bubble transport prediction and uncertainty quantification in lead-cooled fast reactor based on attentional feature fusion. ENGINEERING APPLICATIONS OF ARTIFICIAL INTELLIGENCE, 2026, 180: 115023.