一体化快堆蒸汽发生器热工水力计算方法研究  

Research on Thermal-hydraulic Calculation Method of Steam Generator for Integrated Fast Reactor

作　　者：余奇 朱丽娜[1] 朱桓君 侯斌 YU Qi;ZHU Lina;ZHU Huanjun;HOU Bin(Department of Nuclear Engineering Design,China Institute of Atomic Energy,Beijing 102413,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

出　　处：《原子能科学技术》2025年第S1期71-79,共9页Atomic Energy Science and Technology

基　　金：中核集团集中研发项目。

摘　　要：一体化快堆是钠冷快堆未来发展的重要方向,蒸汽发生器作为反应堆关键设备,其设计对于一体化快堆的建设至关重要。本文采用功率网格方法和固定网格方法分别开展了大型整体式蒸汽发生器稳态及瞬态热工水力计算程序的开发,对均相流方程和三大守恒方程进行离散后采用吉尔算法进行热工参数的求解,并利用俄罗斯在设计中国实验快堆(CEFR)蒸汽发生器过程中不同工况下热工参数的计算值对程序进行了验证。验证结果表明,该程序的计算精度能够适用于大型蒸汽发生器热工水力的计算。在此基础上,开展了大型蒸汽发生器稳态和瞬态热工水力特性的计算,为一体化快堆大型蒸汽发生器的设计奠定了基础。Integrated fast reactors emerge as the future direction for sodium cooled fast reactor systems.Steam generator is critical components in reactor systems.Their design directly impacts integrated fast reactor construction quality.Developing specialized thermal-hydraulic analysis codes becomes an urgent priority.To develop the codes,physical and thermal-hydraulic models was firstly selected.Water side was divided into four regions:subcooled region,nucleate boiling region,film boiling region,and superheated vapor region.The Dittus-Boelter correlation was applied for Nu calculation in the subcooled region.Chen’s correlation was applied to calculate two-phase heat transfer coefficients in the nucleate boiling region.The Groeneveld’s correlation was applied for Nu calculation in the film boiling region.And the Sieder-Tate correlation was applied for Nu calculation in superheated vapor region.Single-phase pressure drop was calculated using the Colebrook-White formula,and two-phase friction pressure drop was calculated using the two-phase friction pressure drop multiplier factor for homogeneous flow.Then the framework was established through meticulous grid generation on the steam generator model,employing moving mesh methodology for steady-state simulations and fixed mesh approach for transient condition analysis.Next the homogeneous flow equation and three conservation equations were discretized.Gill’s algorithm was used to solve the thermal parameters.The calculation results of the code were verified by using the design values of the steam generator of China Experimental Fast Reactor(CEFR).The developed thermal-hydraulic analysis code demonstrates exceptional performance in SG-33 steam generator design calculations,with results matching design parameters within required accuracy thresholds.The relative error of the tube length is always kept below 15%.Transient flow step-change validation tests reveal the code’s dynamic capabilities,requiring 9120 seconds to simulate 380 second transients,resulting in a 24∶1

关 键 词：一体化快堆 蒸汽发生器 热工水力 数值计算 

分 类 号：TL33[核科学技术—核技术及应用]