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GSI-191不同破坏压力材料对应的碎片影响区域半径计算方法研究 被引量:2

Study on the Calculation of Radius of Debris Impact Area for Different Material Destructive Pressures in GSI-191
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摘要 安全壳内高能管道发生破口之后,高速喷射的流体会冲击附近的设备和结构,产生不同类型的碎片。这些碎片会随地坑内的流体迁移到再循环滤网表面上,甚至会穿过滤网进入一回路管道和设备中,堵塞长期冷却循环通道,影响事故后堆芯热量的导出。本文研究了破口喷射参数和不同材料破坏压力对应的碎片影响区域(Zone of Influence)半径计算方法。根据不同的破口类型和破口上游流体参数,计算破口处的喷射压力和质量流量。分析高速喷射流形成的几何形状和压力分布,计算沿喷射流方向不同距离的喷射压力和径向压力,最后根据材料的破坏压力折算成碎片影响区域半径ZOI,可作为电站碎片分析的分析参考。 When the high energy pipe rupture happens inside the containment, the jet from break will impinge the equipment and structure nearby to produce debris. The debris will be transplanted by water in sump to the surface of the strainer, and some of them will go through the strainer to the pipes and equipment of the primary system, which will degrade the capability of the long-term recirculation cooling and the core heat removal after the accident. The research purpose of this paper is the calculation method of the break jet parameters and radius of debris impact area for different material destructive pressures. The paper calculates the injection pressure and mass flux from pipe breaks based on different types of breaks and fluid parameters for upstream ofbreaks, and analyzes the geometry, axial and radial pressure distribution, which determine the radius of debris impact area for different material destructive pressures. It can make reference for the debris analysis for power plant.
作者 王中立
出处 《核科学与工程》 CAS CSCD 北大核心 2016年第1期97-102,共6页 Nuclear Science and Engineering
关键词 碎片影响区域 长期冷却循环 debris impact area long-term recirculation cooling
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参考文献3

  • 1GSI-191 [R] Assessment of Debris Accumulation on PWR Sump Performance,2002.
  • 2NEI-04-07 [ S] Pressurized Water Reactor Sump Performance Evaluation Methodology, 2004.
  • 3ANSI58. 2[S] Design Basis for Light Water Nuclear Power Plants Against the Effects of Postulated Pipe Rupture, 1988.

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