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Dechang Cai

Observed name: De-Chang Cai
ORCID: 0009-0009-4070-361X
Observed ORCID: 0009-0009-4070-361X
OpenAlex ID: A5102552005
Measurement of reactor neutrino oscillation with the first JUNO data
2026 · Angel Abusleme, Thomas Adam, et al. · Nature · 24
Initial performance results of the JUNO detector*
2026 · Angel Abusleme, Thomas Adam, et al. · Chinese Physics C · 17
A drift-flux model for the analysis of low-velocity gas-lead-bismuth two-phase flow in a circular flow channel
2023 · Zihua Liu, Di Wang, et al. · Journal of Mechanical Science and Technology · 4
Numerical simulation of single bubble rising in stagnant lead-bismuth eutectic
2024 · Zihua Liu, Shun Wang, et al. · Journal of Mechanical Science and Technology · 2
Sensitivity analysis of rod rearrangement in criticality safety for PWR fuel assemblies under transportation accidents
2025 · Xin-Ling Dai, De-Chang Cai, et al. · Nuclear Science and Techniques · 1
New approach to evaluate axial deformation of PWR fuel assembly on criticality safety of transport packages under impact accidents
2025 · Xinling Dai, Yanmin Zhang, et al. · Annals of Nuclear Energy · 1
Research on the Propagation Characteristics of Neutron Noise Under Different Core Design
2026 · Lin Guo, Dechang Cai, et al. · Journal of Nuclear Engineering
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Efficient critical safety analysis model for PWR fuel assembly under transport accidents by neutron worth iteration
2026 · Xinling Dai, Dechang Cai, et al. · Annals of Nuclear Energy
Optimization Study and Validation of Reaching Criticality of HPR1000 Unit
2026 · Bo Liu, Dechang Cai, et al. · Springer proceedings in physics
Preliminary Economic Analysis of Accident Tolerant Fuel Based on SiC Cladding and High Uranium Density Pellets
2026 · Ling Ye, Yu Xiang Zhu, et al. · Springer proceedings in physics
LPGPT: a domain-specific autoregressive pretrained transformer for core loading pattern generation
2026 · Hailiang Shi, Changyou Zhao, et al. · SSRN Electronic Journal
Numerical Study of Corrosion-Product Particle Deposition in a Trapezoidal Rib-Wrapped Fuel Rod Channel of a Lead-Bismuth Reactor
2026 · Yicheng Ou, Mingyu Jiang, et al. · SSRN Electronic Journal
Experimental study on circumferential non-uniform heat transfer characteristics in helical tubes
2025 · Xiong Zheng, Xin Wang, et al. · Nuclear Engineering and Design
Experimental Study on Flow Instability in Multi-parallel Helical Tubes
2025 · Xiong Zheng, Yaxin Gao, et al. · Springer proceedings in physics
Numerical Simulation of Thermal Fluctuation Characteristics for Liquid Lead–Bismuth in T-Junction Tube
2025 · Shuqi Meng, Yisong Hu, et al. · Springer proceedings in physics
Neutronic analysis of PWR fuel-assembly bowing based on measurement data
2025 · Xuezhong Li, Dechang Cai, et al. · Nuclear Engineering and Design
Neutronic Analysis of Fuel Assembly Bowing on Pwr
2025 · Xuezhong Li, Dechang Cai, et al. · SSRN Electronic Journal
Works count: 17
Citation count: 49
H-index: 3
I10-index: 2
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