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AP1000核电厂蒸汽发生器主管道发生小破口事故情况下氢气源项分析 被引量:3

The Analysis of Hydrogen Source Term under SB-LOCA in AP1000 Nuclear Power Plant
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摘要 本文采用一体化严重事故分析程序,以AP1000核电厂为研究对象,在以1#SG隔间主管道发生的小破口冷却剂丧失事故情况下,针对不同的破口尺寸及破口位置对氢气源项的影响进行分析。结果表明,氢气的生成量虽然与破口的尺寸有关,但并不呈现明显的变化规律,并且氢气释放的时间段较为集中,其主要来源于燃料包壳外的锆-水反应;而在破口尺寸相同的情况下,当破口位于主管道冷段时,氢气生成速率的峰值最大;同时最大总的氢气累积生成量出现在位于主管道热段的破口处。 Taking AP1000 nuclear power plant as a research subject,an integrated severe accident analysis procedure is adopted to study the impacts of different sizes and locations of the break on the progression of accident and the hydrogen source term under SB-LOCA of primary system in 1#SG compartment. The results show that the yield of hydrogen is related to the break size and without showing a significant change trend,and hydrogen is mainly from zirconium-water reaction;However,under the condition of the same break size,the hydrogen generation rate peaks when the break locates in a cold leg;and the total cumulative hydrogen production peaks when the break locates in a hot leg.
出处 《核安全》 2015年第1期60-64,共5页 Nuclear Safety
基金 国家自然科学基金项目 课题编号51306057 中央高校基本科研业务费专项资金 课题编号201420ZD19
关键词 AP1000 小破口冷却剂丧失事故 氢气源项 AP1000 SB-LOCA hydrogen source term
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