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先进压水堆核电站氢气风险分析 被引量:5

Hydrogen Risk Analysis of Advanced PWR Nuclear Power Plant
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摘要 核电厂在严重事故期间会产生大量氢气并释放到安全壳内,威胁安全壳的完整性。应用氢气风险分析程序GASFLOW对先进压水堆核电站在大破口失水事故叠加应急堆芯冷却系统失效导致的严重事故期间的氢气行为及风险进行分析。结果表明,当气体释放源位于蒸汽发生器隔间时,氢气流动的主要路径为"蒸汽发生器隔间—穹顶空间—操作平台以下隔间";破口隔间的氢气体积浓度分布与源项氢气体积浓度及射流形态有关,非破口区域的氢气体积浓度呈层状分布,在扩散作用下,层状分布向下推移;蒸汽发生器隔间存在着火焰加速(FA)的可能性,但基本可排除燃爆转变(DDT)的可能性,穹顶区域基本可排除FA和DDT的可能性。 In the case of the hypothetical severe accident in a nuclear power plant (NPP) ,a large amount of hydrogen will be generated and released into the contain‐ment ,which may be a threat to containment integrity .The hydrogen risk analysis code GASFLOW was adopted to make the research on hydrogen behavior and risk during the hypothetical severe accident initiated by large break LOCA with failure of emergency core cooling system for advanced PWR NPP .It is shown that if the gas source is in the steam generator (SG) cavity ,the main route of hydrogen flow is “SG room‐dome area‐subcompartments below operating deck” . The hydrogen volume concentration in the cavity with break is affected by the hydrogen fraction of mixture source term and config‐uration of mixture jet ,the hydrogen volume concentration stratification occurs in non‐break areas and the stratification moves downwards with the effect of diffusion .The flame acceleration (FA) may occur in the SG cavity ,while the possibility of deflagration to detonation (DDT ) can be practically excluded ,and the possibilities of FA and DDT can also be practically excluded for the dome area .
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2015年第5期877-883,共7页 Atomic Energy Science and Technology
关键词 严重事故 安全壳 氢气风险 火焰加速 燃爆转变 计算流体力学 severe accident containment hydrogen risk flame acceleration deflagra-tion to detonation CFD
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  • 1TRAVIS J R,SPORE J W,ROYL P,et al.GASFLOW:A computational fluid dynamics code for gases,aerosols and combustion,Vol.1 [M].Karlsruhe,Germany:FZK,2001. 被引量:1
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