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高位排气系统运行瞬态压力载荷分析

Analysis the Pressure Change During the High Point Vent System Running Transient
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摘要 为进一步提高核电厂的安全性,并满足法规对严重事故缓解措施的要求,消除事故过程中大量积聚在反应堆压力容器顶部的不可凝结气体对机组安全造成的重大威胁,我国自主研发的百万千瓦级压水式反应堆在压力容器顶部增设了排放阀门,在事故中通过此路径将大量积聚在反应堆顶部的不可凝结气体排出,这个系统即为高位排气系统。该文通过程序模拟,分析了高位排气系统在运行过程中可能经历的压力载荷。计算结果显示在所分析的工况中,高位排气系统可能经历的过程包括气体到气体、气体到液体的排放,但总体压力载荷冲击幅度不大,不会对系统造成额外风险。 For the purpose that improve the safety of Nuclear Power Plant and meet the law request for severe accident mitigation measure,then avoid inadequate core cooling or impaired natural circulation resulting from the accumulation of non-condensable gases in the Reactor vessel head,the High Point Vent System is designed of 1000 MWe Nuclear Power Plant which is independence projected of China.The basic function of this system is to remove non-condensable gases or steam from the reactor vessel head.This paper will discuss the pressure change during of the high point vent system running transient state by code calculate.The results show that the pressure change is not a main risk for this system.
出处 《科技创新导报》 2015年第22期51-54,共4页 Science and Technology Innovation Herald
关键词 高位排气系统 不可凝气体 氢气 压力载荷 High point vent system Non-condensable gas Hydrogen Pressure change
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参考文献5

  • 1U.S.NRC. "Acceptance Criteria for Reactor Coolant Stem Venting Systems" .10 CFR 50.46a,2003.
  • 2U.S.NRC.RELAP5/MOD3 Code Manual.NUREG/CR-4312,1998.
  • 3U.S.NRC."Follow up Actions resulting from the NRC Staff Reviews Regarding the Three Mile Island Unit 2 Accident", 1979.
  • 4U.S.NRC."elarification of TMI Action Plan Requirements: II.B.1,Reactor Coolant System Vents" .NUREG-0737,1980.
  • 5A.F.Akselrod, T.C.Esselman. " Transient Thermal-hydraulic Analysis of the Reactor Vessel Head Vent System".Elsevier Science Publishers B.V,1993.

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