液态金属快堆螺旋管蒸汽发生器一、二次侧耦合传热数值研究  

Numerical study of coupled heat transfer between primary and secondary sides of helical coiled tube steam generator for liquid metal fast reactor

作　　者：刘佳伦 宁亮 林金鹏 辛杰 李敏 李会雄[3] LIU Jialun;NING Liang;LIN Jinpeng;XIN Jie;LI Min;LI Huixiong(College of New Energy,Xi'an Shiyou University,Xi'an 710065,China;Ningxia Special Equipment Inspection and Testing Institute,Yinchuan 750000,China;State Key Laboratory of Multiphase Flow in Power Engineering,Xi'an JiaoTong University,Xi'an 710049,China)

机构地区：[1]西安石油大学新能源学院,西安710065 [2]宁夏特种设备检验检测院,银川750000 [3]西安交通大学动力工程多相流国家重点实验室,西安710049

出　　处：《核技术》2024年第9期151-162,共12页Nuclear Techniques

基　　金：国家自然科学基金联合基金项目(No.U20B2036);西安石油大学研究生创新与实践能力培养计划(No.YCS23114167);陕西省自然科学基础研究计划项目(No.2023-JC-YB-350)资助。

摘　　要：螺旋管蒸汽发生器是液态金属快堆中能量传递的核心设备,其运行的稳定性、安全性对核电站的运行有至关重要的影响。为此,本文构建了液态金属快堆螺旋管蒸汽发生器一次侧、二次侧耦合传热的三维数值模型,分别基于经济合作与发展组织核能署(The Organisation for Economic Co-operation and Development,OECD/NEA)物性手册和美国国家标准与技术研究院(National Institute of Standards and Technology,NIST)数据库建立液态金属和水-水蒸气变物性计算关联式,采用Lee相变模型计算二次侧水-水蒸气蒸发过程中两相间的质量传递。基于实验数据,分别对本文模型一次侧传热以及二次侧传热的计算可靠性进行了验证。最后以铅铋快堆为例,研究了不同一次侧进口参数下蒸汽发生器一、二次侧之间的耦合传热特性,并与传统水冷堆进行了对比。结果表明:在同等条件下,相比于传统水冷堆,一次侧采用铅铋液态金属时,一、二次侧之间的壁面热流密度明显提升,热流密度峰值可达1439.97 kW·m^(-2),比水冷堆相应数值提升5~6倍,这导致二次侧管内气相蒸发过程明显加剧,体积含气率急剧上升;同时,一、二次侧之间的沿程热流密度分布更加不均匀,沿程热流密度分布相对偏差值比水冷堆相应数值增大3~4倍。随着一次侧进口铅铋温度从350℃增大到450℃,一、二次侧之间的壁面热流密度随之增大,对应的热流密度峰值从950.7 kW·m^(-2)增大到1439.97 kW·m^(-2),提升约1.5倍,同时一、二次侧之间的沿程热流密度分布更加不均匀,不均匀度增大20%。[Background]Helical coiled tube steam generator is the core equipment for energy transfer in a liquid metal fast reactor(LMFR),which transfers the heat released from the core on the primary side to the working mass on the secondary side,generates steam and pushes the turbine to do work.The stability and safety of its operation have a crucial impact on the operational safety,economy and reliability of nuclear power plants.[Purpose]This study aims to propose a numerical simulation method using computational fluid dynamics(CFD)software for the coupled heat transfer calculation of two-phase fluids in the steam generator of LMFR.[Methods]First of all,a threedimensional numerical model of coupled primary and secondary heat transfer in the steam generator of LMFR was constructed,and the correlation equations of liquid metal and water-vapor variability were established based on the OECD(The Organisation for Economic Co-operation and Development)physical property handbook and the NIST(National Institute of Standards and Technology)database.Then,the Lee phase transition model was used to calculate the mass transfer between the two phases during the evaporation of water-vapor on the secondary side.Finally,the lead-bismuth fast reactor was taken as an object,the coupled heat transfer characteristics between the primary and secondary sides of the steam generator under different primary-side inlet parameters were investigated and compared with the conventional water reactors.[Results&Conclusions]The results show that,under the same conditions,compared with the traditional water reactor,the wall heat flux between the primary and secondary sides is significantly increased when lead-bismuth liquid metal is used in the primary side,and the peak heat flux can reach 1439.97 kW·m^(-2),which is 5~6 times higher than that of the corresponding value of the water reactor,which leads to a significant intensification of the vapor evaporation process in the tube of the secondary side,and the volumetric vapor volume fraction rate rises shar

关 键 词：液态金属快堆 螺旋管蒸汽发生器 三维耦合传热模型 水-水蒸气两相流 沸腾相变 

分 类 号：TL353.13[核科学技术—核技术及应用]