Neutronic-Thermal Coupling Analyses of U-50Zr Helical Cruciform Fuel Concepts Based on OpenMC Code and MOOSE Framework

Springer proceedings in physics 2026

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Authors: Yiliang Dong, Qinglong Wen

DOI: 10.1007/978-981-95-2732-8_10

Cited by: 0

References: 21

Fields of Study & Subjects

Nuclear Materials and Properties Nuclear reactor physics and engineering Nuclear Engineering Thermal-Hydraulics

References 21