Language :
中文
Tengfei Zhang
Home
Scientific Research
Research Field
Paper Publications
Patents
Published Books
Research Projects
Teaching Research
Teaching Resources
Teaching Information
Teaching Achievement
Awards and Honours
Admission Information
Student Information
My Album
Blog
MOBILE Version
Paper Publications
Current position:
Home
>
Scientific Research
>
Paper Publications
[1] Preliminary Research on a Multi-Physics Coupling Platform for Heat Pipe Reactors Hedongli Gongcheng/Nuclear Power Engineering, 2021,
[2] Conceptual Design of a Reduced Moderation Long-Life Heavy Water Cooled Thorium Small Modular Reactor Hedongli Gongcheng/Nuclear Power Engineering, 2021,
[3]Tengfei Zhang. Optimal Batch Size Growth for Wielandt Method and Superhistory Method Nuclear Science and Engineering, 2021,
[4]Tengfei Zhang. The Application of the Combined Fission Matrix Theory in Fast Reactors FRONTIERS IN ENERGY RESEARCH, 2021,
[5] A variational nodal approach to 2D/1D pin resolved neutron transport for pressurized water reactors Nuclear Science and Engineering, 2017,
[6] An improved variational nodal method for the solution of the three-dimensional steady-state multi-group neutron transport equation Nuclear Engineering and Design, 2018,
[7] A Variational Nodal Approach to 2D/1D Pin Resolved Neutron Transport for Pressurized Water Reactors Nuclear Science and Engineering, 2017,
[8] 中子扩散三维非均匀变分节块法及平源加速方法研究 核动力工程, 2018,
[9]Tengfei Zhang. Parallelization of the pin resolved variational nodal method Transactions of the American Nuclear Society, 2018,
[10]Tengfei Zhang. Generalized partitioned matrix acceleration of variational nodal method AISTech - Iron and Steel Technology Conference Proceedings, 2018,
[11]Tengfei Zhang. 小型铅-铋冷却快堆提棒事故核热耦合研究 核动力工程, 2019,
[12] A hybrid acceleration method to pin-by-pin calculations using the heterogeneous variational nodal method Annals of Nuclear Energy, 2019,
[13] Preliminary Research on a Multi-Physics Coupling Platform for Heat Pipe Reactors 热管反应堆多物理耦合平台初步研究 Hedongli Gongcheng/Nuclear Power Engineering, 2021,
[14] Conceptual Design of a Reduced Moderation Long-Life Heavy Water Cooled Thorium Small Modular Reactor 重水冷却钍基长寿命模块化小堆概念设计研究 Hedongli Gongcheng/Nuclear Power Engineering, 2021,
[15] Studies on calculation models of ASTRA critical facility benchmark using OpenMC Annals of Nuclear Energy, 2021,
total69 2/5
first
previous
next
last
Page
沪ICP备05052060 版权所有©上海交通大学
Click:
