首页> 外文会议>10th International Conference on Nuclear Engineering, Vol.1, Apr 14-18, 2002, Arlington, Virginia >INTEGRATED ANALYSIS OF MECHANICAL AND THERMAL HYDRAULIC BEHAVIOR OF GRAPHITE STACK IN CHANNEL-TYPE REACTORS IN CASE OF A FUEL CHANNEL RUPTURE ACCIDENT
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INTEGRATED ANALYSIS OF MECHANICAL AND THERMAL HYDRAULIC BEHAVIOR OF GRAPHITE STACK IN CHANNEL-TYPE REACTORS IN CASE OF A FUEL CHANNEL RUPTURE ACCIDENT

机译:通道破裂反应器中石墨层在通道式反应器中的力学和热力学行为的综合分析

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The paper discusses the methodology and a computational exercise analyzing the processes taking place in the graphite stack of an RBMK reactor in case of a pressure tube rapture caused by overheating. The methodology of the computational analysis is implemented in integrated code U_STACK which models thermal-hydraulic and mechanical processes in the stack with a varying geometry, coupled with the processes going on in the circulation loop and accident localization (confinement) system. Coolant parameters, cladding and pressure tube temperatures, pressure tube ballooning and rupture, coolant outflow are calculated for a given accident scenario. Fluid parameters, movement of graphite blocks and adjacent pressure tubes bending after the tube rapture are calculated for the whole volume of the core. Calculations also cover additional loads on adjacent fuel channels in the rapture zone, reactor shell, upper and lower plates. Impossibility of an induced pressure tube rapture is confirmed.
机译:本文讨论了在过热引起压力管破裂的情况下,RBMK反应堆石墨堆中发生的过程的方法和计算练习。计算分析的方法在集成代码U_STACK中实现,该代码对具有不同几何形状的堆栈中的热工和机械过程进行建模,并与循环回路和事故定位(约束)系统中正在进行的过程相结合。针对给定的事故场景,计算出冷却液参数,包层和压力管温度,压力管膨胀和破裂,冷却液流出。对于岩心的整个体积,计算了流体参数,石墨块的运动以及管破裂后相邻的压力管弯曲。计算还涵盖了在易爆区域,反应堆壳体,上下板上的相邻燃料通道上的额外载荷。确认不可能引起压力管破裂。

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