摘要
采用MELCOR程序,以600MW级核电厂为研究对象,在以大破口失水事故为始发事件的严重事故中,针对不同的破口尺寸及破口位置对堆芯内锆-水反应及堆腔内熔融堆芯与堆腔混凝土之间的相互作用(MCCI)中氢气源项的影响进行敏感性分析。结果表明,在大破口始发的严重事故中,不同的破口尺寸对氢气源项的影响不大;而在破口尺寸相同的情况下,破口发生在主管道热段时,产氢速率的峰值最大;破口发生在主管道冷段时,累积的总产氢量最大。
The hydrogen source, which generates through oxidation of Zircaloy by steam and molten core concrete interaction in cavity, during the severe accident induced by large LOCA for the 600MW NPP was analyzed in this paper by using MELCOR code, including the sensitivity impacts or the different break sizes and locations. The results are summarized as follows： during the large LOCA severe accident, it has no substantial effect on hydrogen source with a different break size; when there is the same break size, the laydrogen generation rate peaks when the break locates in a hot leg; and the total cumulative hydrogen production peaks when the break locates in a cold leg.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2007年第5期69-74,108,共7页
Nuclear Power Engineering
