科研 - 贺 亚男
| 项目编号 | 项目名称 | 项目来源 | 起讫时间 | 承担角色 | 项目类别 |
|---|---|---|---|---|---|
| 20230828 | 反应性引入工况下SiC包壳失效行为研究及分析方法开发服务合同 | 其他 | 2023-08~2024-08 | Leader | 横向项目 |
| 202308178 | 燃料-包壳化学相互作用（FCCI）模型研究 | 其他 | 2023-08~2024-08 | Leader | 横向项目 |
| 12205230 | 多物理场耦合作用下氟盐冷却高温堆螺旋燃料流动与传热机理研究 | 国家自然科学基金项目 | 2023-01~2025-12 | 负责人 | 纵向项目 |
| 20220507 | 先进燃料研发进展咨询技术服务合同 | 中国核电工程有限公司 | 2022-01~2022-03 | 负责人 | 横向项目 |
| 20210997 | SiC复合包壳的先进燃料失效概率精细化分析方法开发 | 中广核研究院有限公司 | 2021-09~2022-11 | 负责人 | 横向项目 |
| xzy012021017 | 基于跨尺度耦合的弥散型X燃料元件起泡机理研究 | 校内项目-基本业务费 | 2021-08~2023-12 | 负责人 | 其它 |
| 论文标题 | 作者 | 发表/完成日期 | 期刊名称 |
|---|---|---|---|
| 核反应堆系统多维度多物理场耦合有限元分析研究 | 巫英伟，贺亚男*，章静，田文喜，苏光辉，秋穗正 | 2024-02-01 | 原子能科学技术 |
| Development of a hybrid model for fuel performance analysis of spherical fuel elements under normal conditions | Yanan He, Chen Gu, Chaoqun Deng, Yingwei Wu, Guanghui Su, Wenxi Tian, Suizheng Qiu | 2023-03-06 | Journal of Nuclear Materials |
| 基于在线耦合的球形燃料元件温度场计算 | 顾晨，贺亚男*，邓超群，巫英伟，章静，田文喜，苏光辉，秋穗正 | 2023-02-01 | 核动力工程 |
| TRISO包覆燃料颗粒裂变产物扩散释放特性研究 | 郑军强，贺亚男*，章 静，巫英伟，田文喜，苏光辉，秋穗正 | 2022-12-01 | 核动力工程 |
| Modification of FROBA code and its application in Thermal-Mechanical analysis of the Single-Cell thermionic fuel element | Kailin Lu, Haoyu Liao, Yanan He, Yingwei Wu, Jing Zhang, Hao Yao, GH Su, Suizheng Qiu | 2022-09-15 | Annals of Nuclear Energy |
| An effective method for modeling 1D two-phase two-fluid six-equation model with automatic differentiation approach | Yuhang Niu, Yanan He, Bowen Qiu, Fengrui Xiang, Chaoqun Deng, Yuanming Li, Jing Zhang, Yingwei Wu, Wenxi Tian, GH Su, Suizheng Qiu | 2022-09-01 | Progress in Nuclear Energy |
| Preliminary development of a multi-physics coupled fuel performance code for annular fuel analysis under normal conditions | Yanan He, Yuhang Niu, Fengrui Xiang, Yingwei Wu, Jing Zhang, Guanghui Su, Wenxi Tian, Suizheng Qiu | 2022-07-01 | Nuclear Engineering and Design |
| Finite element based fuel performance investigation of U3Si2–FeCrAl design under normal and RIA conditions | Chaoqun Deng, Yanan He*, Fengrui Xiang, Yingwei Wu, Jing Zhang, Wenxi Tian, Guanghui Su, Suizheng Qiu | 2022-07-01 | Progress in Nuclear Energy |
| Multi-Objective Optimization Design of Plate-type Fuel via Co-simulation Method | Jiatong Tan, Quan Li, Bo Zhao, Chao Ma, Yingwei Wu, Yuanming Li, Jing Zhang, Yanan He, Tianzhou Ye, Cheng Zhang, Wenxi Tian, Guanghui Su, Suizheng Qiu | 2022-05-01 | Annals of Nuclear Energy |
| A new method to simulate dispersion plate-type fuel assembly in a multi-physics coupled way | Fengrui Xiang, Yanan He, Yuhang Niu, Chaoqun Deng, Yingwei Wu, Kunpeng Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu | 2022-02-01 | Annals of Nuclear Energy |
| Investigation on thermo-mechanical performance of fully ceramic microencapsulated fuel | Cheng Zhang, Yingwei Wu, Yanan He, Yuanming Li, Shichao Liu, Jing Zhang, Wenxi Tian, GH Su, Suizheng Qiu, Junmei Wu | 2021-12-01 | Journal of Nuclear Materials |
| Automatic differentiation approach for solving one-dimensional flow and heat transfer problems | Yuhang Niu, Yanan He, Fengrui Xiang, Jing Zhang, Yingwei Wu, Wenxi Tian, Guanghui Su, Suizheng Qiu | 2021-09-15 | Annals of Nuclear Energy |
| Development of a transient module based on FROBA-ROD code and assessment for fuel rod performance under reactivity-initiated accident | Haoyu Liao, Kailin Lu, Chenxi Li, Hao Yao, Yanan He, Yingwei Wu, GH Su, Suizheng Qiu | 2021-09-15 | Annals of Nuclear Energy |
| Application of High-order Analysis Code Solving Five-equation Two-phase Flow Problem Based on MOOSE | Yuhang NIU, Wei LU, Yanan HE, Chaoqun DENG, Fengrui XIANG, Yingwei WU, Guanghui SU, Suizheng QIU, Wenxi TIAN, Yang YU, Tianyu LU | 2021-08-20 | Atomic Energy Science and Technology |
| Development and Validation of Fuel Rod Performance Transient Analysis Code Based on MOOSE Platform | Yanan He Development and Validation of Fuel Rod Performance Transient Analysis Code Based on MOOSE Platform | 2021-08-20 | Atomic Energy Science and Technology |
| 3D-2D coupling multi-dimension simulation for the heat pipe micro-reactor by MOOSE&SAM | Yukun Zhou, Jun Wang, Zehua Guo, Yanan He, Yapei Zhang, Suizheng Qiu, GH Su, Michael L Corradini | 2021-08-01 | Progress in Nuclear Energy |
| Preliminary prediction for survival time of fuel rod under critical heat flux | Yanan He, Koroush Shirvan, Yingwei Wu, Guanghui Su | 2021-02-01 | Annals of Nuclear Energy |
| Analysis for fuel rod performance under LOCA based on the FROBA-ROD 2.0 code | Haoyu Liao, Chenxi Li, Yanan He, Yingwei Wu, Yapei Zhang, Wenxi Tian, GH Su, Suizheng Qiu | 2021-01-01 | International Journal of Advanced Nuclear Reactor Design and Technology |
| Fuel performance optimization of U3Si2-SiC design during normal, power ramp and RIA conditions | Yanan He, Koroush Shirvan, Yingwei Wu, GH Su | 2019-11-01 | Nuclear Engineering and Design |
| Integrating a multi-layer deformation model in FRAPTRAN for accident Tolerant fuel analysis | Yanan He, Koroush Shirvan, Yingwei Wu, Guanghui Su | 2019-11-01 | Annals of Nuclear Energy |
(创新港)
