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U2241282

Funded outputs count: 5
Funder award ID: U2241282
OpenAlex ID: G53681300
Development and validation of an advanced thermal-hydraulic analysis program for helical coil once-through steam generator in lead-based cooled fast reactor
2026 · Zhipeng Liu, Gaoman Zhao, et al. · Progress in Nuclear Energy
Thermal-hydraulic analysis of helical coil once-through steam generator for lead-based cooled fast reactor using a program based on two-fluid model
2025 · Zhipeng Liu, Pengrui Qiao, et al. · Annals of Nuclear Energy · 3
Corrosion behavior of molybdenum in liquid sodium
2025 · Chunsong Liu, Hongchen Xiang, et al. · Annals of Nuclear Energy · 2
A transparent hybrid metal halide glassy scintillation screen for high-resolution fast neutron radiography
2025 · Zi’an Zhou, Jinxiao Zheng, et al. · Nature Communications · 18
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Progress in understanding the formation and deposition behaviors of corrosion and oxidation products in lead-cooled fast reactors
2025 · Zhengang Duan, Hongchen Xiang, et al. · Progress in Nuclear Energy · 8
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