适用于新型PWR燃料组件的CHF关系式的开发及应用
doi: 10.13832/j.jnpe.2019.01.0008
Development and Application of a New CHF Correlation for PWR Fuel Assembly
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摘要: 以中国核动力研究设计院（NPIC）的棒束临界热流密度（CHF）实验数据为依据，基于具有自主知识产权的子通道分析程序CORTH，采用最小偏离泡核沸腾比（DNBR）点法开发了适用于新型压水堆（PWR）燃料组件的CHF关系式（CF-DRW关系式）并对其进行了应用分析。典型事故分析结果表明，采用CF-DRW关系式的计算结果相比FC-2000关系式具有相当或者更大的热工裕量。
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关键词:
- 压水堆（PWR） /
- 燃料组件 /
- 临界热流密度（CHF）关系式 /
- 子通道分析
Abstract: Based on the bundle CHF test database of NPIC, the minimum DNBR point method is applied in this study to develop a new CHF correlation named CF-DRW correlation for the PWR fuel assembly to couple with the subchannel code CORTH. The results of typical accidents analysis indicate that the DNBR thermal margin of CF-DRW correlation is almost equivalent or even larger than the FC-2000 correlation.-
Key words:
- PWR /
- Fuel assembly /
- Critical Heat Flux (CHF) correlation /
- Sub-channel analysis
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