中国实验快堆单组件完全堵流后钠沸腾的预测  

Prediction of sodium boiling caused by total blockage of a single subassembly inlet in the Chinese experimental fast reactor

作　　者：石晓波[1] 罗锐[1] 王洲[1] 杨献勇[1] 穆瑞云[1] 

机构地区：[1]清华大学热能工程系,北京100084

出　　处：《清华大学学报（自然科学版）》2004年第11期1558-1561,1566,共5页Journal of Tsinghua University(Science and Technology)

摘　　要：为预测正常功率下快堆单个燃料组件的瞬间完全堵流导致的后续事故序列及其潜在的破坏能力,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。在此基础上对中国实验快堆(CEFR)在此事故工况下的冷却剂沸腾进行了预测。计算结果表明:对于CEFR,沸腾的过程中也出现了实验中观测到的出口处流量波动和通过组件盒的热流通量的快速增长。SCARABEEBE+1实验中,干涸发生之前,沸腾持续了大约2.2s;对于CEFR,沸腾开始后0.3s便发生了干涸。造成这一差异的主要原因是CEFR的燃料组件规模和单位体积的热功率更大。The total instantaneous blockage of a single subassembly inlet in the liquid metal cooled fast breeder reactor LMFBR may cause very severe consequences which should be predicted. The SCARABEE BE+1 test until onset of cladding motion was simulated to verify the numerical model. The model was then applied to the Chinese experimental fast reactor CEFR to predict the phenomenon after a blockage. The results show that the outlet flow oscillation and rapid increase of the heat flux through the hexcan-wall in the SCARABEE BE+1 test also occur during boiling in CEFR. In the SCARABEE BE+1 test, sodium reentry delays the onset of dryout until 2.2 s after boiling onset, while boiling lasts only 0.3 s before dryout onset in the CEFR. The difference occurs mainly because the CEFR subassembly is composed of many more fuel pins with much larger power per unit volume.

关 键 词：快堆 钠沸腾 子通道 堵流 

分 类 号：TL433[核科学技术—核技术及应用]