Plate-type water cooled high flux reactor thermal hydraulic analysis codes: A review for evaluation model development

Progress in Nuclear Energy 2026

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Authors: Yebing Zhang, Meng Lv, Lei Shi, Ding She, Heng Xie

DOI: 10.1016/j.pnucene.2026.106323

Cited by: 0

References: 42

Fields of Study & Subjects

Nuclear Engineering Thermal-Hydraulics Nuclear reactor physics and engineering Heat transfer and supercritical fluids

References 42