Numerical investigation of flow blockage on heat transfer characteristics in 7 helical-cruciform fuel rod bundle

Annals of Nuclear Energy 2026

View at publisher

Authors: Z.H. Li, C. Hu, B.H. Yan, L.S. Wang

DOI: 10.1016/j.anucene.2026.112319

Cited by: 1

References: 38

Fields of Study & Subjects

Heat transfer and supercritical fluids Nuclear Engineering Thermal-Hydraulics Nuclear Materials and Properties

References 38