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材料导报  2022, Vol. 36 Issue (11): 21040054-5    https://doi.org/10.11896/cldb.21040054
  金属与金属基复合材料 |
金属燃料辐照模型关于孔隙率的改进及快堆金属燃料性能分析程序开发
王挺1, 高业栋1,2, 恽迪1,3, 王冠4,5, 周毅2, 张坤2, 郭子萱2, 吕亮亮2
1 西安交通大学核科学与技术学院,西安 710049
2 中国核动力研究设计院,成都 610213
3 西安交通大学动力工程多相流国家重点实验室,西安 710049
4 中国科学院近代物理研究所,兰州 730000
5 中国科学院大学,北京 100049
Improvement of Metal Fuel Irradiation Model on Porosity and Development of Metal Fuel Performance Analysis Code for Fast Neutron Reactor
WANG Ting1, GAO Yedong1,2, YUN Di1,3, WANG Guan4,5, ZHOU Yi2, ZHANG Kun2, GUO Zixuan2, LYU Liangliang2
1 School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China
2 Nuclear Power Institute of China, Chengdu 610213, China
3 State Key Laboratory of Multi-phase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an 710049, China
4 Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China
5 University of Chinese Academy of Sciences, Beijing 100049, China
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摘要 随着钠冷快堆及铅冷快堆的发展,金属燃料的应用前景初步显现,开发适用于钠冷快堆金属燃料的性能分析程序对快堆金属燃料的发展和应用具有重要意义。本工作在调研总结了燃料芯体的孔隙率对导热系数、力学参数的影响后,提出了新的金属燃料芯体导热系数和力学参数模型。此外,在参考金属燃料相关文献中金属燃料的其他辐照行为模型后,本工作改进了传热模型及力学模型,利用FORTRAN-90开发了适用于钠冷快堆棒状金属燃料的燃料性能分析程序,该程序可用于预测典型的金属燃料辐照行为。
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王挺
高业栋
恽迪
王冠
周毅
张坤
郭子萱
吕亮亮
关键词:  孔隙率  热导率  杨氏模量  快堆  金属核燃料  性能分析程序    
Abstract: With the development of sodium-cooled fast reactors and lead-cooled fast reactors, the application prospect of metal fuel has initially appeared. The development of metal fuel performance analysis code suitable for sodium-cooled fast reactors is of great significance to the development and application of metal fuels. After investigating and summarizing the influence of the porosity of the pellet on the thermal conductivity and mechanical properties, a new model of the thermal conductivity and mechanical properties of the pellet is proposed. In addition, the heat transfer model and mechanical model were improved after referring to other radiation behavior models of metal fuel in related literatures, a fuel performance analysis code suitable for sodium-cooled fast reactor rod metal fuels was developed using FORTRAN-90. This code can be used to predict typical irradiation behaviors of metal fuels.
Key words:  porosity    thermal conductivity    Young's modulus    fast neutron reactor    metallic nuclear fuel    performance analysis code
发布日期:  2022-06-09
ZTFLH:  TL352  
通讯作者:  diyun1979@xjtu.edu.cn   
作者简介:  王挺,西安交通大学硕士研究生,在恽迪教授的指导下进行研究学习,目前研究方向为快中子反应堆金属燃料性能分析仿真。
恽迪,西安交通大学教授、博士研究生导师。2001年本科毕业于清华大学工程物理系,2010年5月获美国伊利诺伊大学香槟分校博士学位。2010年6月至2015年8月担任美国阿贡国家实验室工程师。2015年9月起归国就任于西安交通大学核科学与技术学院,入选2017年国家海外高层次人才引进计划,2017年陕西省百人计划等。主要从事核能相关的研究工作,研究方向涉及核燃料与材料的实验表征、事故容错核燃料开发以及核燃料性能仿真、裂变气体行为分析等,发表SCI论文 30余篇。
引用本文:    
王挺, 高业栋, 恽迪, 王冠, 周毅, 张坤, 郭子萱, 吕亮亮. 金属燃料辐照模型关于孔隙率的改进及快堆金属燃料性能分析程序开发[J]. 材料导报, 2022, 36(11): 21040054-5.
WANG Ting, GAO Yedong, YUN Di, WANG Guan, ZHOU Yi, ZHANG Kun, GUO Zixuan, LYU Liangliang. Improvement of Metal Fuel Irradiation Model on Porosity and Development of Metal Fuel Performance Analysis Code for Fast Neutron Reactor. Materials Reports, 2022, 36(11): 21040054-5.
链接本文:  
http://www.mater-rep.com/CN/10.11896/cldb.21040054  或          http://www.mater-rep.com/CN/Y2022/V36/I11/21040054
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