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压水堆环形燃料结构热工水力分析方法研究 被引量:7

Methodology Study of Thermal-hydraulic Analysis for PWR Annular Fuel Assembly Array
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摘要 以秦山二期压水堆为参考堆型,对压水堆环形燃料结构进行热工水力分析方法研究。应用SAAF程序分析了从11×11到15×15等5种不同排列方式中不同尺寸的环形燃料棒的热工水力性能,综合最小偏离泡核沸腾比、压降和燃料芯块温度等参数确定了环形燃料组件最佳排列方式为13×13。本文研究结果为相关专业分析提供了初始计算模型。 A typical Qinshan Phase-Ⅱ PWR plant was selected as the base case for methodology study of thermal-hydraulic analysis for the best array of annular fuel assembly applied in the PWR core. A range of arrays from 11×11 to 15× 15 for differ- ent sizes was investigated by using a sub-channel analyzer named SAAF. On the consid- eration of minimum departure from nucleate boiling ratios, pressure drops and fuel temperatures, the most promising option was found to be the 13 ×13 array of annular fuel assembly. The calculation results in this paper provide initial calculation model for correlative analysis.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2015年第8期1374-1379,共6页 Atomic Energy Science and Technology
关键词 压水堆 环形燃料 热工水力 最佳排列方式 PWR annular fuel thermal-hydraulics the best array
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  • 1CARPENTER D, FEINROTH H, LAHODA E J, et al. High performance fuel design or next generation PWRs Final report[R]. USA Mas- sachusetts Institute of Technology, 2006.
  • 2于平安,朱瑞安,于真烷,等.核反应堆热工分析[M].上海:上海交通大学出版社,2002:139-200.
  • 3HAN Kyuhyun, CHANG Soonheung. Develop- ment of a thermal-hydraulic analysis code for an- nular fuel assemblies [J]. Nuclear Engineering and Design, 2003, 16: 1-3.
  • 4HAN Kyuhyun, CHANG Soonheung. Thermal- hydraulic analysis of liquid metal reactors with annular fuel rods [C]//The 11th International Topical Meeting on Nuclear Reactor Thermal- Hydraulics (NURETH-11). IS. 1.]: [s. n.], 2005.

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