周建军｜三峡大学｜学者主页

期刊论文

2026

基于OpenMC/COBRA-EN的压水堆物理-热工耦合计算方法研究

袁显宝，樊东方，官昌啸，张彬航，张永红，周建军，唐海波

《核技术》

2026

摇摆条件下换热器传热管流致振动特性研究

林京君，袁显宝，周建军，杜晓超，毛璋亮

《核动力工程》

2026

Uncertainty informed calibration of thermal-hydraulic models for nuclear reactor via integrated neural network and optimization algorithm framework

Qingwen Xiong, Xianbao Yuan, Sen Zhang, Jianjun Zhou, Zhangliang Mao, Yonghong Zhang

Reliability Engineering & System Safety

DOI

2026

CFD Study on Fluid Flow and Heat Transfer Characteristics of Heat Exchanger Under Swing Conditions

Zhou Jianjun, Lin Jingjun, Yuan Xianbao, Du Xiaochao, Zhangliang Mao

Nuclear Science and Engineering

DOI

2025

摇摆条件下反应堆蒸汽发生器传热管振动特性分析

周建军，林京君，陈文祥，蒋翰林

《南方能源建设》

DOI

2024

压水堆破口事故下裂变产物源项释放及衰变热分析

袁显宝，彭珏钦，张彬航，毛璋亮，唐海波，魏靖宇，周建军

《核技术》

2024

Three-dimensional CFD model for the coking of supercritical n-decane in circular and elliptical tubes

Chen Zhang, Jianjun Zhou, Jiajun Zhao, Dong-Sheng Wen, Hui Gao

Chemical Engineering and Science

DOI

2023

钠冷快堆绕丝环形燃料组件流动特性分析

袁显宝，雷荫先，郭跃峰，周建军，杜晓超，张永红，张彬航，谭超，杨森权

《核科学与工程》

2022

快堆带绕丝环形燃料棒热工水力特性分析

袁显宝，郭跃峰，周建军，张永红，张彬航，谭伟

《核科学与工程》

2022

Cooling performance optimization of supercritical hydrocarbon fuel via bi-directional flow pattern

Chen Zhang, Hui Gao, Jiajun Zhao, Jianjun Zhou, Dongshen Wen

Applied Thermal Engineering

DOI

2021

百万千瓦级压水堆严重事故下裂变产物释放分析

袁显宝，魏靖宇，张永红，张彬航，周建军，毛璋亮，杜晓超，石强，郭盼

《核科学与工程》

2020

基于SCDAP/RELAP5的严重事故后压水堆泄压注水安全分析

袁显宝，谭伟，黄家胜，张永红，张彬航，李双，周建军，杜晓超

《核科学与工程》

2020

熔盐冷却球床堆分流板结构优化设计

周建军，袁显宝，毛璋亮，肖仁政，马小强

《核科学与工程》

2018

基于MAAP4的压水堆严重事故进程分析

黄家胜，袁显宝，毛璋亮，林钦，夏寅泳，周建军，肖仁政，马小强

《核科学与工程》

2014

液体燃料熔盐堆三维稳态分析程序开发

周建军，张大林，秋穗正，苏光辉，田文喜，巫英伟

《原子能科学技术》

2014

Three dimensional neutronic/thermal-hydraulic coupled simulation of MSR in transient state condition

Jianjun Zhou, Dalin Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian, Yingwei Wu

Nuclear Engineering and Design

DOI

Dynamic coking simulation of supercritical n-decane in circular tubes

Chen Zhang, Hui Gao, Jiajun Zhao, Jianjun Zhou, Xiaolong Ma, Dongshen Wen

Fuel

DOI

数据集

2026

Validation Dataset for VERA Benchmark Problems 6 and 7 Based on the OpenMC/COBRA-EN Coupled Code

Yuan Xianbao, fan dong fang, Guan Changxiao, Binhang Zhang, Zhang Yonghong, Zhou Jianjun, Tang Haibo

ScienceDB

DOI

周建军

个人简介

精选作品

期刊论文

基于OpenMC/COBRA-EN的压水堆物理-热工耦合计算方法研究

摇摆条件下换热器传热管流致振动特性研究

Uncertainty informed calibration of thermal-hydraulic models for nuclear reactor via integrated neural network and optimization algorithm framework

CFD Study on Fluid Flow and Heat Transfer Characteristics of Heat Exchanger Under Swing Conditions

摇摆条件下反应堆蒸汽发生器传热管振动特性分析

压水堆破口事故下裂变产物源项释放及衰变热分析

Three-dimensional CFD model for the coking of supercritical n-decane in circular and elliptical tubes

钠冷快堆绕丝环形燃料组件流动特性分析

快堆带绕丝环形燃料棒热工水力特性分析

Cooling performance optimization of supercritical hydrocarbon fuel via bi-directional flow pattern

百万千瓦级压水堆严重事故下裂变产物释放分析

基于SCDAP/RELAP5的严重事故后压水堆泄压注水安全分析

熔盐冷却球床堆分流板结构优化设计

基于MAAP4的压水堆严重事故进程分析

液体燃料熔盐堆三维稳态分析程序开发

Three dimensional neutronic/thermal-hydraulic coupled simulation of MSR in transient state condition

Dynamic coking simulation of supercritical n-decane in circular tubes

数据集

Validation Dataset for VERA Benchmark Problems 6 and 7 Based on the OpenMC/COBRA-EN Coupled Code

研究方向