快堆钠-水蒸汽发生器热工水力稳态综合性能研究  

Study on Thermal-hydraulic Steady-state Comprehensive Performance of Fast Reactor Sodium-water Steam Generator

作　　者：肖常志[1] 杨红义[1] 张大林[2] 沈格宇 秋穗正[2] 路远 张魁 黄源彬 XIAO Changzhi;YANG Hongyi;ZHANG Dalin;SHEN Geyu;QIU Suizheng;LU Yuan;ZHANG Kui;HUANG Yuanbin(Department of Nuclear Engineering Design,China Institute of Atomic Energy,Beijing 102413,China;School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an 710049,China)

机构地区：[1]中国原子能科学研究院核工程设计研究所,北京102413 [2]西安交通大学核科学与技术学院,陕西西安710049

出　　处：《原子能科学技术》2024年第2期328-336,共9页Atomic Energy Science and Technology

摘　　要：钠-水直流蒸汽发生器作为分隔钠冷快堆二、三回路的重要屏障,有着非常重要的地位。为分析蒸汽发生器的流动换热特性,西安交通大学搭建了快堆钠-水蒸汽发生器综合性能试验台架,开展了一系列稳态实验,并自主开发了一维两相热工水力设计程序。从稳态实验中选取低功率、中等功率以及满功率5个典型工况开展DeCOSS程序稳态计算。在对实验数据以及计算结果进行归一化处理后,对钠侧轴向温度分布以及蒸发器出口钠侧、水侧出口温度进行对比验证。可发现不同功率工况下,DeCOSS程序计算结果均与实验数据符合良好,验证了蒸汽发生器自主化设计和分析程序的正确性。此外,获取的实验数据也可反之修正DeCOSS程序计算方法,为今后钠-水蒸汽发生器开展相关课题的研究奠定基础。The sodium-heated once-through steam generator(OTSG)plays an important role in separating the second and third circuits of sodium cooled fast reactor(SFR).Once the heat transfer pipe breaks,it will cause serious sodium water reaction,which will seriously affect the availability,economy and reliability of nuclear power plant operation.In order to analyze the flow heat transfer characteristics of the steam generator,based on the China Demonstration Fast Reactor(CFR600)once-through steam generator designed by the China Institute of Atomic Energy,Xi’an Jiaotong University built the PUSA test platform for the comprehensive performance of the fast reactor sodium-water steam generator according to the equal height,equal pressure and equal heat exchange tube diameter,and carried out a series of steady-state and transient comprehensive performance experiments.At the same time,the one-dimensional two-phase thermal hydraulic design code was developed independently.By comparing the experimental data with the calculation results of the steam generator design and the verification analysis code DeCOSS,this paper aimed to verify the rationality of the steam generator design and the accuracy of the steady-state calculation of the design analysis code.Firstly,the self-developed fast reactor sodium-water steam generator two-phase flow thermal fluid design and verification analysis code DeCOSS was used.Five typical working conditions of low power(heating power 7.18%and 12.41%rated power),medium power(heating power 27.87%and 29.74%rated power)and full power(heating power 100%rated power)were selected from the steady-state experiment to carry out steady-state calculation of DeCOSS code.Then,the above thermal hydraulic parameters such as temperature and flow rate obtained under the five stable working conditions of low power,medium power and full power were divided by the temperature and flow rate under full power respectively.After normalization,the DeCOSS code was compared and verified with the axial temperature distribution on the

关 键 词：钠-水蒸汽发生器试验台架 DeCOSS程序 热工水力分析 

分 类 号：TL333[核科学技术—核技术及应用]