期刊文献+

Simulation of the mixing process in FCIs with hydrodynamic fragmentation model

Simulation of the mixing process in FCIs with hydrodynamic fragmentation model
下载PDF
导出
摘要 Fuel Coolant Interactions (FCIs) are important issues in nuclear reactor severe accident analysis. In FCIs, fragmentation model of molten droplets is a key factor to estimate degree of possible damage. In this paper, the mixing process in FCIs is studied by the simulation of MIXA experiment with hydrodynamic fragmentation model. The result shows that hydrodynamic fragmentation model underestimates the fragmentation rate of high temperature molten droplets under the condition of low Weber numbers. It is concluded that models based on thermal fragmentation mechanism should be adopted to analyze the FCI process and its consequence. Fuel Coolant Interactions (FCIs) are important issues in nuclear reactor severe accident analysis. In FCIs, fragmentation model of molten droplets is a key factor to estimate degree of possible damage. In this paper, the mixing process in FCIs is studied by the simulation of MIXA experiment with hydrodynamic fragmentation model. The result shows that hydrodynamic fragmentation model underestimates the fragmentation rate of high temperature molten droplets under the condition of low Weber numbers. It is concluded that models based on thermal fragmentation mechanism should be adopted to analyze the FCI process and its consequence.
出处 《Nuclear Science and Techniques》 SCIE CAS CSCD 2007年第4期242-246,共5页 核技术(英文)
基金 National Natural Science Foundation of China (No.50576050)
关键词 核反应堆 燃料冷冻作用 事故 燃料熔化 Severe accident, FCI, Molten fuel droplet, Fragmentation, MIXA
  • 相关文献

参考文献10

  • 1Kondo S A, Brear D J, Tobita Y, et al. Status and achievement of assessment program for SIMMER-Ⅲ, a multiphase, multicomponent code for LMFR safety analysis, Proceedings of Eighth International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, 1997, Japan.
  • 2Morita K, Kondo S A, Tobita Y, et al. SIMMER-Ⅲ application to fuel-coolant interactions, Proceedings of the OECD/CSNI Specialists Meeting on Fuel-Coolant Interactions, 1997, Japan.
  • 3Berthoud G, Crecy F, Meignen R. Description of premixing with the MC3D Code including molten jet behavior modeling: Comparison with FARO Experiment results, Proceedings of the OECD/CSNI Specialists Meeting on Fuel- Coolant Interactions, 1997, Japan.
  • 4Corradini M L, Kim B J, Oh M D. Progress in Nuclear Energy, 1988, 22(1): 1-117.
  • 5Cronenberg A W, Grolmest M A. Nuclear Safety, 1975, 16(6): 683-700.
  • 6Denham M K, Tyler A P. Fletcher D F. Experiments of the mixing of molten uranium dioxode with water and initial comparison with CHYMES code calculations, Proceedings of Fifth International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, 1992, USA.
  • 7Fletcher D F, Denham M K. Validation of the CHYMES mixing model, Proceedings OECD/CSNI Specialists Meeting on Fuel-Coolant Interactions, 1993, USA.
  • 8Meyer L. QUEOS: An experimental investigation of the premixing phase with hot spheres, Proceedings of Eighth International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, 1997, Japan.
  • 9Cao X W, Tobita Y. Journal of Nuclear Science and Technology, 2001, 38(9): 721-728.
  • 10Pilch M, Erdman C. International Journal of Multiphase, 1987, 13(6): 741-757

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