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大功率先进压水堆压力容器外部冷却能力研究 被引量:4

Study on External Reactor Vessel Cooling Capacity for Advanced Large Size PWR
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摘要 目前压力容器外部冷却(ERVC)作为严重事故管理策略中压力容器内熔融物滞留(IVR)的一部分已得到了广泛应用。本文采用RELAP5系统安全分析程序定性研究一些流动参数和边界条件(如进出口面积、冷却水的入口温度、下封头处的加热功率、下封头处流道的间隙尺寸及注水高度等)对大功率先进压水堆压力容器外部冷却的自然循环能力产生的效应,它为结构的设计和系统的瞬态响应行为提供了一定的分析依据。 External reactor vessel cooling (ERVC ) is widely adopted as a part of in-vessel retention (IVR) in severe accident management strategies .In this paper ,some flow parameters and boundary conditions , eg ., inlet and outlet area , water inlet temperature ,heating power of the lower head ,the annular gap size at the position of the lower head and flooding water level ,were considered to qualitatively study the effect of them on natural circulation capacity of the external reactor vessel cooling for an advanced large size PWR by using RELAP5 code .And the calculation results provide some basis of analysis for the structure design and the following transient response behavior of the system .
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2014年第2期277-284,共8页 Atomic Energy Science and Technology
关键词 大功率先进压水堆 压力容器外部冷却 自然循环能力 advanced large size PWR external reactor vessel cooling natural circulation capacity
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参考文献6

  • 1THEOFANOUS T G, LIU C, ADDITON S, et al. In-vessel cool ability and retention of a core melt[R]. America: Department of Energy, 1996. 被引量:1
  • 2THEOFANOUS T G, SYRI S. The cool ability limits of a reactor pressure vessel lower head[J]. Nuclear Engineering and Design, 1997, 169(1- 3) : 59-76. 被引量:1
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  • 4PARKR J, HA K S, KIM S B, et al. Two- phase natural circulation flow of air and water in a reactor cavity model under an external vessel cooling during a severe accident[J]. Nuclear En- gineering and Design, 2006, 236(23): 2 424- 2 430. 被引量:1
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二级参考文献8

  • 1THEOFANOUS T G, SYRI S.The coolability limits of a reactor pressure vessel lower head [J].Nuclear Engineering and Design, 1997, 169(1-3): 59-76. 被引量:1
  • 2PARK J H, JEONG Y H, BAEK W P, et al.An assessment methodology for in-vessel corium retention by external reactor vessel cooling during severe accidents in PWRs[J].Annals of Nuclear Energy, 2001, 28(12): 1 237-1 350. 被引量:1
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  • 5CHU T Y, BENTZ J H, SLEZAK S E, et al.Ex-vessel boiling experiments: Laboratory and reactor-scale testing of the flooded cavity concept for in-vessel core retention: Part Ⅱ.Reactor-scale boiling experiments of the flooded cavity concept for in-vessel core retention[J].Nuclear Engineering and Design, 1997, 169(1-3): 89-99. 被引量:1
  • 6YANG J, DIZON M B, CHEUNG F B, et al.CHF enhancement by vessel coating for external reactor vessel cooling[C]∥ICAPP’04.Pittsburgh, USA: [s.n.], 2004: 4 041. 被引量:1
  • 7PARK R J, HA K S, KIM S B, et al.Two-phase natural circulation flow of air and water in a reactor cavity model under an external vessel cooling during a severe accident [J].Nuclear Engineering and Design,2006, 236(23): 2 424-2 430.. 被引量:1
  • 8CHENG X, YANG Y H, OUYANG Y, et al.Role of passive safety system in chinese nuclear power development[J].Science and Technology of Nuclear Installations, 2009: 573026. 被引量:1

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