冯文培｜成都理工大学｜学者主页

期刊论文

2026

基于ICoCo规范的快堆燃料组件多物理场耦合性能分析方法

杨广亮，刘振海，王浩煜，辛勇，李垣明，冯文培，董思凡，陈红丽

《原子能科学技术》

2026

Numerical simulation of indoor radon transport and evaluation of ventilation strategies for mitigation efficiency

Luoxian He, Wenpei Feng, Xue Zhang, Xilin Zhang, Ziqiang Zou, Ruicheng Zhong, Dan Wu

Annals of Nuclear Energy

DOI

2026

Safety analysis of small modular natural circulation lead-cooled fast reactors SNCLFR-100 during unprotected loss of heat sink and protected loss of heat sink transients

Yulin Yan, Guanghui Yu, Zhixing Gu, Wei Chen, Tianxin Song, Sangang Li, Zhiwei Zhang, Wenpei Feng

Kerntechnik

DOI

2025

高温液态铅铋池内高压过冷水射流喷放演化特性研究

严钰淋，余光辉，辜峙钘，宋天鑫，李三刚，冯文培，张牧昊

《核动力工程》

DOI

2025

Investigation of flow and heat transfer in the liquid metal cooled subchannel with rough surfaces

Wei Li, Meng Zhang, Xue Zhang, Wenpei Feng

Case Studies in Thermal Engineering

DOI

2025

Investigation into the flow and heat transfer characteristics in liquid metal cooled narrow rectangular channel with rough surfaces

Xue Zhang, Wenpei Feng, Xiaolong Yang, Hongxing Yu, Jian Deng, Sijia Du

Case Studies in Thermal Engineering

DOI

2024

Effect of Corrosion Behavior on the Heat Transfer Performance of Fuel Cladding in Lead-Cooled Fast Reactors

Wenpei Feng, Shangdong Yang, Hongxing Yu, Xingqing Lu, Xue Zhang, Zhixing Gu

DOI

2024

Study on the turbulent Prandtl number model for liquid metal flow and heat transfer in a narrow rectangular channel

Xue Zhang, Hongxing Yu, Deng Jian, Sijia Du, Wang Xiaoyu, Wenpei Feng

Frontiers in Energy Research

DOI

2024

Study on flow and heat transfer characteristics of liquid metal flow in narrow rectangular channels under high heat flux

Xue Zhang, Wenpei Feng, Hongxing Yu, Jian Deng, Sijia Du, Xiaoyu Wang

Frontiers in Energy Research

DOI

2024

Heat transfer characteristics analysis of heat pipe based on COMSOL

Rui Pan, Ke-Fan Zhang, Wei-Xiang Wang, Ao-Guang Wu, Wenpei Feng, Xiao Luo, Hong-Li Chen

Annals of Nuclear Energy

DOI

2023

铅铋堆蒸汽发生器传热管破裂事故三维程序开发及验证

辜峙钘，余红星，黄代顺，严明宇，申亚欧，冯文培，龚政宇

《核动力工程》

2023

Preliminary Study of Oxygen Mass Transfer in the Primary Circuit of Lead Cooled Fast Reactor

Wenpei Feng, Chong Qin, Ke-Fan Zhang, Guang-Liang Yang, Wei-Xiang Wang, Wen-Shun Duan, Rui Pan, Hong-Li Chen

Social Science Research Network

DOI

2022

Validation of the TWOPORFLOW code for the core analysis of liquid metal-cooled reactor with selected experiments

Wenpei Feng, U. Imke, Kang-Long Zhang, V. Sánchez-Espinoza, Hong-Li Chen

Nuclear Engineering and Design

DOI

2022

Investigation on the Simulation of Turbulent Heat Transfer of Liquid Metal Flow in a Narrow Rectangular Channel

Xue Zhang, Hongxing Yu, Jian Deng, Si-Jia Du, Xi-Lin Zhang, Z. Zou, Wenpei Feng, Yao-Xiang Zhang

Volume 8: Computational Fluid Dynamics (CFD) and Applications

DOI

2022

Integral Simulation on the Thermo-Mechanical Behavior of the UMo/Al Dispersion Fuel Plate Using Finite Element Method

Guang-Liang Yang, Wenpei Feng, Tao Ding, Hong-Li Chen

Volume 15: Student Paper Competition

DOI

2022

Thermal-Hydraulic Safety Analysis of Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100 Core Based on Porous Medium Approach

Wenpei Feng, Guang-Liang Yang, Ke-Fan Zhang, Chong Qin, Xiao-mei Luo, Tao Ding, Hong-Li Chen

Volume 7B: Thermal-Hydraulics and Safety Analysis

DOI

2021

基于统一耦合框架的堆芯物理热工耦合程序的开发及验证

姜荣，冯文培，陈红丽，强胜龙，李治刚，潘俊杰，张喜林，罗晓

《四川大学学报(自然科学版)》

DOI

2021

Development of a multi-physics coupling system based on ICoCo interface and its validation on NEA-OECD core transient benchmark

Wenpei Feng, Rong Jiang, Hong-Li Chen, Sheng-Long Qiang, Zhaohu Gong, Zhi-Gang Li, Junjie Pan, Wenbo Zhao, Xi-Lin Zhang, Xiao Luo, Xue Zhang

DOI

2021

Study on the subcooled boiling pressure drop for downward flow in a narrow rectangular channel

Xue Zhang, Wenpei Feng, J. Zhang, Hong-Li Chen

DOI

2021

Development of oxygen/corrosion product mass transfer model and oxidation-corrosion model in the lead-alloy cooled reactor core

Wenpei Feng, Xue Zhang, Lian-Kai Cao, Shuai Wang, Hong-Li Chen

DOI

2020

Simulation of oxygen mass transfer in fuel assemblies under flowing lead-bismuth eutectic

Wenpei Feng, Xue Zhang, Hong-Li Chen

DOI

2020

Experimental study on flow instability for downward flow in a narrow rectangular channel with flow pattern transition

Xue Zhang, Wenpei Feng, Jie Zhang, Simao Guo, W. Ding, Hong-Li Chen

DOI

2019

Simulation study on flow instability in parallel narrow rectangular channels for downward flow with different heating modes

Xue Zhang, Wenpei Feng, Jie Zhang, Hong-Li Chen

Annals of Nuclear Energy

DOI

2017

熔盐实验堆稳态运行模式研究

王浩然，张娜，李永琦，冯文培，周蓝宇，曾文杰

《新型工业化》

预印本

2026

Thermal performance and hierarchical lightweight optimization of a fluid-pipe radiator for space nuclear power systems

Bing Xiang, Wenpei Feng, 陆杏清, Xue Zhang, Zhike Lan, Hongxing Yu

SSRN Electronic Journal

DOI

2026

Mechanism of rod-bowing-induced circumferential heat-transfer deterioration in a tight He-Xe gas-cooled rod bundle with conjugate heat transfer

Wenpei Feng, 陆杏清, Hongxing Yu, Zhike Lan, He Xiaoqiang, Wenshun Duan, Xue Zhang

SSRN Electronic Journal

DOI

2026

Multiphysics propagation of oxidation-corrosion effects in a lead-cooled fast reactor

Wenpei Feng, Hongxing Yu, Xue Zhang, 陆杏清, Zhike Lan, R Li

SSRN Electronic Journal

DOI

2026

Erosion Damage Behavior and Mechanisms of an Fe Substrate Induced by Solid Pb Particles in Lead–Bismuth Reactor Coolant

Zhaole Wang, Wenpei Feng, Xue Zhang, Hongxing Yu, Zhike Lan, R Li

SSRN Electronic Journal

DOI

冯文培

精选作品

期刊论文

基于ICoCo规范的快堆燃料组件多物理场耦合性能分析方法

Numerical simulation of indoor radon transport and evaluation of ventilation strategies for mitigation efficiency

Safety analysis of small modular natural circulation lead-cooled fast reactors SNCLFR-100 during unprotected loss of heat sink and protected loss of heat sink transients

高温液态铅铋池内高压过冷水射流喷放演化特性研究

Investigation of flow and heat transfer in the liquid metal cooled subchannel with rough surfaces

Investigation into the flow and heat transfer characteristics in liquid metal cooled narrow rectangular channel with rough surfaces

Effect of Corrosion Behavior on the Heat Transfer Performance of Fuel Cladding in Lead-Cooled Fast Reactors

Study on the turbulent Prandtl number model for liquid metal flow and heat transfer in a narrow rectangular channel

Study on flow and heat transfer characteristics of liquid metal flow in narrow rectangular channels under high heat flux

Heat transfer characteristics analysis of heat pipe based on COMSOL

铅铋堆蒸汽发生器传热管破裂事故三维程序开发及验证

Preliminary Study of Oxygen Mass Transfer in the Primary Circuit of Lead Cooled Fast Reactor

Validation of the TWOPORFLOW code for the core analysis of liquid metal-cooled reactor with selected experiments

Investigation on the Simulation of Turbulent Heat Transfer of Liquid Metal Flow in a Narrow Rectangular Channel

Integral Simulation on the Thermo-Mechanical Behavior of the UMo/Al Dispersion Fuel Plate Using Finite Element Method

Thermal-Hydraulic Safety Analysis of Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100 Core Based on Porous Medium Approach

基于统一耦合框架的堆芯物理热工耦合程序的开发及验证

Development of a multi-physics coupling system based on ICoCo interface and its validation on NEA-OECD core transient benchmark

Study on the subcooled boiling pressure drop for downward flow in a narrow rectangular channel

Development of oxygen/corrosion product mass transfer model and oxidation-corrosion model in the lead-alloy cooled reactor core

Simulation of oxygen mass transfer in fuel assemblies under flowing lead-bismuth eutectic

Experimental study on flow instability for downward flow in a narrow rectangular channel with flow pattern transition

Simulation study on flow instability in parallel narrow rectangular channels for downward flow with different heating modes

熔盐实验堆稳态运行模式研究

预印本

Thermal performance and hierarchical lightweight optimization of a fluid-pipe radiator for space nuclear power systems

Mechanism of rod-bowing-induced circumferential heat-transfer deterioration in a tight He-Xe gas-cooled rod bundle with conjugate heat transfer

Multiphysics propagation of oxidation-corrosion effects in a lead-cooled fast reactor

Erosion Damage Behavior and Mechanisms of an Fe Substrate Induced by Solid Pb Particles in Lead–Bismuth Reactor Coolant

研究方向