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Duoyu Jiang

Observed names: Duoyu JIANG, JIANG Duoyu
ORCID: 0009-0004-7847-8861
Observed ORCID: 0009-0004-7847-8861
OpenAlex ID: A5063644926
A discontinuous finite element method based on B-spline wavelet on the interval for solving first-order neutron transport equation with discrete ordinate (SN) angular discretisation
2021 · Hewei Guo, Wei Chen, et al. · Annals of Nuclear Energy · 10
A new continuous finite element SN method for solving first-order neutron transport equation
2022 · Hewei Guo, Wei Chen, et al. · Annals of Nuclear Energy · 8
Coupled Monte Carlo and Thermal-Hydraulics Modeling for the Three-Dimensional Steady-State Analysis of the Xi’an Pulsed Reactor
2023 · Duoyu Jiang, Peng Xu, et al. · Energies · 6
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Preliminary feasibility analysis of Heat Pipe Cooled Bimodal Space Nuclear Reactor
2021 · Xiaoyan Tian, Huaqi Li, et al. · Progress in Nuclear Energy · 6
SphiNx: A SN-DFEM neutron transport code based on the MOOSE framework
2025 · Hu Zhang, Da Li, et al. · Nuclear Engineering and Technology · 5
Transient multi-physics coupling analysis of the Xi'an Pulsed Reactor under pulsed condition
2024 · Duoyu Jiang, Peng Xu, et al. · Annals of Nuclear Energy · 5
Three-dimensional transient analysis of Xi’an pulsed reactor by the coupled neutronics and thermal-hydraulics code
2022 · Xinyi Zhang, Xinbiao Jiang, et al. · Annals of Nuclear Energy · 5
Investigation on the impact of thermal-kernel effect of lithium hydride on the reactivity of nuclear propulsion particle bed reactor
2019 · Lipeng Wang, Duoyu Jiang, et al. · Annals of Nuclear Energy · 4
Steady-state analysis of Xi’an Pulse Reactor based on the multi-physics coupling method
2024 · Tianliang Hu, Duoyu Jiang, et al. · Annals of Nuclear Energy · 3
Numerical solution of static and spatial kinetics self-adjoint angular flux neutron transport equation
2024 · Duoyu Jiang, Peng Xu, et al. · Nuclear Engineering and Technology · 3
Transient Simulation and Parameter Sensitivity Analysis of Godiva Experiment Based on MOOSE Platform
2023 · Lipeng Wang, Shuwei Guo, et al. · Energies · 3
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FCMI analysis of multiphysics coupling of fuel rods at the end of cycle of Xi’an pulsed reactor
2025 · Zhaohao Wang, Jinkai Zhang, et al. · Annals of Nuclear Energy · 2
Hydrogen redistribution in fuel of Xi'an pulsed reactor based on RMC and COMSOL
2026 · Jingjie ZOU, Lipeng WANG, et al. · Nuclear Techniques
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Validation of self-adjoint angular flux neutron transport code with TAKEDA benchmark
2026 · Duoyu Jiang, Peng Xu, et al. · Journal of Nuclear Science and Technology
Accelerated solution methods for self-adjoint angular flux neutron transport equations based on scattering matrix decoupling
2025 · Duoyu Jiang, Peng Xu, et al. · Nuclear Engineering and Technology
Works count: 16
Citation count: 62
H-index: 5
I10-index: 1
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