基于氧化腐蚀特性的铅铋堆单棒核-热-材耦合研究  

Neutronics-thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics

作　　者：季旭 柴翔 张乐福[1,2] 刘晓晶 JI Xu;CHAI Xiang;ZHANG Lefu;LIU Xiaojing(School of Mechanical Engineering,Shanghai Jiao Tong University,Shanghai 200240,China;Shanghai Digital Nuclear Reactor Technology Intergration Innovation Center,Shanghai 200240,China)

机构地区：[1]上海交通大学机械与动力工程学院,上海200240 [2]上海市数值反应堆技术融合创新中心,上海200240

出　　处：《核技术》2024年第11期139-149,共11页Nuclear Techniques

基　　金：上海市2020年度技术带头人项目(No.20XD1434100)资助。

摘　　要：铅铋堆的氧化腐蚀受温度、氧浓度、时间等多因素影响,同时氧化层的生长也改变了堆芯热工水力和中子物理参数,因此,研究铅铋堆的氧化腐蚀场、热工水力场和中子物理场的耦合作用对铅铋堆应用有重要意义。本工作基于面向对象的多物理场仿真环境(Multiphysics Object-Ori1ented Simulation Environment,MOOSE)搭建了核-热-材多物理场耦合框架,开展了单棒在基准工况下的核-热-材耦合分析,并研究了氧浓度对关键耦合参数的影响。结果表明:基准工况下氧化腐蚀10000 h后氧化层平均厚度约为10μm,燃料最大温升为16 K,k_(inf)下降10^(-4);氧浓度升高可以极有效地抑制磁铁矿溶解,但是对Fe-Cr尖晶石生长的促进作用较小。[Background]Liquid lead-bismuth eutectic(LBE)corrosion and dissolution of structural materials pose significant challenges in the application of lead-bismuth-cooled fast reactors(LFRs).The use of oxygen as an inhibitor emerges as a promising approach to mitigate the corrosion of structural materials by liquid LBE.The oxidative corrosion in LFRs is influenced by various physical parameters within the reactor,including temperature,oxygen concentration,and time.Concurrently,the growth of the oxide layer on the cladding surface exacerbates the heat transfer between the cladding and the coolant,thereby influencing the thermal-hydraulic and neutron physics parameters of the core.Understanding the corrosion protection of structural materials and multi-physics characteristics is crucial issue for LFRs.[Purpose]This study aims to investigate the coupled mechanisms of neutron physics,thermal-hydraulics,and oxidative corrosion,along with the distribution of the oxide layer in lead-bismuth reactors.[Methods]A neutronics-thermal-hydraulics-material coupling framework was developed to investigate the variations in multi-physics parameters and oxide layer distribution in the LFR fuel rod under oxidative corrosion conditions.First of all,based on the Multiphysics Object-Oriented Simulation Environment(MOOSE),the framework was developed to couple three modules:neutron physics,thermal-hydraulics,and oxidative corrosion,and conduct simulation calculations.Thereafter,various lead-bismuth reactor oxide layer growth-removal models were encompassed into a MOOSE-based oxidative corrosion module,named Seal,and the Martinelli model was adopted in subsequent simulations after comparison with experimental values.Then,the neutron physics module was solved by the open-source neutron diffusion equation solver Moltres and the thermal-hydraulics module calculation was performed by MOOSE's Navier-Stokes and Heat Conduction modules.Two coupling relationships in the coupling framework,i.e.,(1)the neutron physics module for transferring power distri

关 键 词：核-热-材耦合 氧化腐蚀 铅铋堆 面向对象的多物理场仿真环境 

分 类 号：TL99[核科学技术—核技术及应用]