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钠冷快堆单个燃料组件冷却剂沸腾的数值模拟 被引量:4

Coolant boiling numerical simulation of subassembly for liquid metal cooled fast breeder reactor
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摘要 在正常功率下快堆单个燃料组件的瞬间完全堵流可能会产生相当严重的后果 ,对其后续事故序列及其潜在的破坏能力进行预测是必要的。对模拟这种现象的SCARABEEBE +1实验在包壳流动之前的阶段进行了数值模拟。程序中采用了两流体、六方程模型来描述沸腾及两相流动 ,应用子通道方法来对基本方程进行离散化 ,以半隐数值方法进行了求解。计算结果与实验观测相吻合 ,这表明该程序可以比较准确地预测单个燃料组件在瞬间完全堵流之后 ,包壳流动之前的行为。 The total instantaneous inlet blockage of a sing le subassembly (TIB) in LMFBR may cause very severe consequences which should be p redicted. A numerical simulation for the SCARABEE BE+1 test from the formation o f blockage till the onset of cladding motion has been performed. In the calculat ion model, the two-fluid conservation equations are discretized by subchannel a pproach and solved by semi-implicit numerical method. Predictions made by the m odel agree well with the experimental observation. The agreement shows that the model is reasonable and could be applied to the analysis of accidents caused by TIB.
出处 《核科学与工程》 CSCD 北大核心 2004年第4期312-317,共6页 Nuclear Science and Engineering
关键词 燃料组件 快堆 冷却剂 沸腾 两相流动 流体 吻合 正常 六方 行为 LMFBR sodium boiling subchannel blockage
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参考文献6

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同被引文献25

  • 1王宏大,常海萍,常国强.封闭腔体内水和钠钾合金热驱动换热数值分析[J].工程热物理学报,2008,29(9):1564-1566. 被引量:1
  • 2石晓波,罗锐,王洲.体热源沸腾池的建模及其验证[J].核科学与工程,2005,25(1):55-60. 被引量:1
  • 3石晓波,罗锐,王洲.快堆单个燃料组件完全堵流事故的建模及其验证[J].核动力工程,2006,27(1):37-42. 被引量:2
  • 4王红艳,吴宜灿.ITER中国液态锂铅实验包层模块液态金属流动MHD效应数值模拟[J].核科学与工程,2006,26(2):173-177. 被引量:7
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