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作 者:张钰浩[1,2] 赵海琦 沈熙昊 袁晓晓 宋海洁 陆道纲 隋丹婷[1,2] ZHANG Yuhao;ZHAO Haiqi;SHEN Xihao;YUAN Xiaoxiao;SONG Haijie;LU Daogang;SUI Danting(School of Nuclear Science and Engineering,North China Electric Power University,Beijing 102206,China;Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy,Beijing 102206,China)
机构地区:[1]华北电力大学核科学与工程学院,北京102206 [2]非能动核能安全技术北京市重点实验室,北京102206
出 处:《原子能科学技术》2024年第S02期271-283,共13页Atomic Energy Science and Technology
基 金:河北省自然科学基金优秀青年基金(A2023502006);北京市科协2023-2025年度青年人才托举工程(BYESS2023091)。
摘 要:钠冷快堆是第四代先进核能系统的重要堆型之一。池式钠冷快堆安全裕量大,但结构较为复杂,其堆内一回路循环流动呈多尺度、复杂空间、多路径、三维流动等特点,给池式钠冷快堆计算与实验带来一定困难。近年来,计算流体力学(CFD)的快速发展为解决上述问题提供了重要技术路径,本文对池式钠冷快堆复杂空间内流动与传热特性三维数值模拟研究进行综述。对于全堆一体化整体计算,获取池式钠冷快堆典型对称/非对称工况下的三维温度场分布及关键热工参数瞬态变化,评价其余热排出能力;对于局部部件或区域精细化计算,获取局部三维流动与传热特征参数,也为全堆一体化计算提供关键输入。相关研究为池式钠冷快堆安全稳定运行及设计优化提供重要支撑。Sodium-cooled fast reactor(SFR)is one of important type in the fourth-generation advanced nuclear energy system.The primary system of SFR adopts the layout of loop-type or pool-type.Pool-type SFR is equipped with more complex structures,but has a larger safety margin with higher safety.Flow in pool-type SFR features the characteristics of multi-scale,complex space,multi-path and three-dimensional(3D)flow,which brings some difficulties for calculation,analysis and experiment.At present,there are few experimental data for pool-type SFR,and the traditional system analysis code is difficult to reflect the three-dimensional characteristics of multi-path and complex flow heat transfer process in the reactor.In recent years,with the rapid development of computational fluid dynamics(CFD),researchers have carried out overall three-dimensional numerical simulation and refined computational analysis of key equipment or local areas for pool-type SFR.In the present work,the research of three-dimensional numerical simulation on flow and heat transfer characteristics in complex space of pool-type SFR was reviewed combined with the recent research achievements of the authors’research team.For the integrated simulation of whole reactor,three-dimensional temperature distributions and transient variations of key thermal parameters under typical symmetric/asymmetric conditions of pool-type SFR are obtained,and the residual heat removal capacity is evaluated.For the simulation of key internals and local regions,refined three-dimensional flow and heat transfer characteristic parameters can be obtained,which also provide key input for integrated simulation of whole reactor.The relevant researches provide important numerical support for the safety,stable operation and design optimization of pool-type SFR.
关 键 词:池式钠冷快堆 池式复杂空间 多路径流动 传热特性 三维数值模拟
分 类 号:TL33[核科学技术—核技术及应用]
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