期刊文献+

数值堆热工流体程序CVR-PACA验证及典型应用 被引量:1

Validation and Typical Application of Thermal-hydraulic Code Analysis in Numerical Reactor with CVR-PACA Code
下载PDF
导出
摘要 谱元方法是一种高精度的数值计算方法,采用该方法开发了数值堆高精度热工水力并行CFD计算程序CVR-PACA。应用CVR-PACA对单棒光棒通道湍流流场、3×3光棒棒束湍流流场、Matis-H压水堆棒束通道基准题、19棒带绕丝组件通道湍流流场进行了仿真计算。通过与实验测量值对比,研究定量验证了大涡模拟(LES)模型及非稳态雷诺时均(URANS)模型对各类棒束通道流场预测的准确性。算例在建模过程中采用网格分裂技术实现了复杂几何的纯六面体网格划分,用于支撑谱元方法计算。研究较为全面地积累了高精度谱元方法模拟流场流动及换热的建模经验,获取了各类棒束通道内丰富的流动和换热细节,获得的建模经验能更加精准有力地指导相关设计的优化改进。 Spectral element method(SEM)is a high-order numerical method.A high-precision parallel CFD code CVR-PACA for thermal-hydraulic analysis of numerical reactor was developed by using this method.In this paper,CVR-PACA was employed to model and predict turbulent flow in single bare rod,3×3 bare rod bundle,Matis-H benchmark and 19 wire-wrapped rod bundle,aiming to validate the predicting capability of large eddy simulation(LES)model and unsteady Reynolds-averaged(URANS)model within the typical applications of thermal-hydraulic analysis in fuel assembly of reactor core.Spatial discretization for complicated geometries was also achieved with full-hexahedral mesh using mesh splitting method.Much more modeling experience of high-precision CFD code CVR-PACA were accumulated during the calculation processes and abundant flow and heat transfer details in various rod bundle channels were obtained,while result from CVR-PACA could provide more thermal-hydraulic details for design optimization.
作者 王明军 鞠浩然 赵民富 李伟卿 刘天才 胡长军 杨文 田文喜 秋穗正 苏光辉 WANG Mingjun;JU Haoran;ZHAO Minfu;LI Weiqing;LIU Tiancai;HU Changjun;YANG Wen;TIAN Wenxi;QIU Suizheng;SU Guanghui(School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an 710049,China;Division of Reactor Engineering Technology Research,China Institute of Atomic Energy,Beijing 102413,China;School of Computer and Communication Engineering,University of Science and Technology Beijing,Beijing 100083,China)
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2021年第9期1569-1580,共12页 Atomic Energy Science and Technology
基金 国家重点研发计划重点专项(2017YFB0202300)。
关键词 湍流搅混 稠密栅元 搅混翼 绕丝棒束 大涡模拟模型 非稳态雷诺时均模型 谱元方法 turbulent mixing tight lattice mixing vane wire-wrapped rod bundle large eddy simulation model unsteady Reynolds-averaged model spectral element method
  • 相关文献

参考文献3

二级参考文献22

  • 1OLDEKOP W, BERGER H D, ZEGGEL W. General features of advanced pressurized water reactors with improved fuel utilization[J].Nu- clear Technology, 1982, 59:212-227. 被引量:1
  • 2UCHIKAWA S, OKUBO T, KUGO T, et al. Investigations on innovative water reactor for flexible fuel cycle (LFWR) [C] // Proceedings of GLOBAL. Tsukuba, Japan..[s. n. ], 2005. 被引量:1
  • 3CHENG X, LIU X J, YANG Y H. A mixed core for supereritical water-cooled reactors [J]. Nuclear Engineering and Technology, 2008, 40 (1) : 1-10. 被引量:1
  • 4KRAUSS T, MEYER T. Experimental investi- gation of turbulent transport of momentum and energy in a heated rod bundle[J]. Nuclear Engi- neering and Design, 1998, 180: 185-206. 被引量:1
  • 5TRUPP A C, AZAD R S. The structure of tur- bulent flow in triangular array rod bundles[J]. Nuclear Engineering and Design, 1975, 32: 47- 84. 被引量:1
  • 6TRIPPE G, WEINBERG D. Non-isotropic eddy viscosities in turbulent flow through rod bundles [M] // Turbulent Forced Convection in Channels and Bundles.. Vol. 1. KAKAC S, SPALDING D B. Washington: Hemisphere Publishing Corpo- ration. 1979. 505. 被引量:1
  • 7SEALE W J. Turbulent diffusion of heat be- tween connected flow passages[J]. Nuclear Engi- neering and Design, 1979, 54: 183-195. 被引量:1
  • 8REHME K. Simple method of predicting friction factors of turbulent flow in non-circular channels [J].International Journal of Heat and Mass Transfer, 1973, 16: 933-950. 被引量:1
  • 9REHME K. The structure of turbulent flow through rod bundles [J]. Nuclear Engineering and Design, 1987, 99: 141-154. 被引量:1
  • 10MEYER L, REHME K. Large-scale turbulence phenomena in compound rectangular channels [J]. Experimental Thermal and Fluid Science, 1994, 8: 286-304. 被引量:1

共引文献24

同被引文献9

引证文献1

二级引证文献5

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部