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Methodology for a numerical simulation of an insertion or a drop of the rod cluster control assembly in a PWR

机译:压水堆中棒束控制组件插入或落下的数值模拟方法

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摘要

In a pressurised water reactor, the rod cluster control assembly is a system which controls the neutronic activity of the core. It consists of long rods, connected by a spider fixture and a cylindrical system for the control drive mechanism. At its withdrawn position, the activity of the core is maximum, and at its completely inserted position, the activity of the core vanishes. In case of emergency, an effective way to shutdown the reactor is to let it drop under its own weight. An other way to verify the efficiency of the rod cluster control assembly is the insertion test. It consists in inserting the rod into its guides and in checking if the reaction friction force is not high enough to block the movement of the rod cluster control assembly. We present in this paper a methodology for a numerical simulation of an insertion or a drop of the rod cluster control assembly into its guides (discontinuous and continuous guides, guide thimble). A numerical model is elaborated in which many loads are taken into account: fluid load, gravity and friction force between the rod and the guide. The numerical results are compared to experimental measurements obtained from a full-scale structure. A good agreement between the calculated and the measured data is observed. The numerical model takes into account the possible deflection of the guide. It shows clearly that the friction force cannot be neglected when the guide is bowed. So one can locate a faulty guiding system by examining the reaction force during the insertion test. Then, the numerical model can help the decider to make his choice among different rod cluster/fuel assembly components.
机译:在压水反应堆中,棒束控制组件是控制堆芯中子活动的系统。它由长杆组成,长杆通过星形固定装置和用于控制驱动机构的圆柱系统连接。在其撤回位置,芯的活动最大,而在其完全插入的位置,芯的活动消失。在紧急情况下,关闭反应堆的一种有效方法是让其自行下落。验证棒束控制组件效率的另一种方法是插入测试。它包括将杆插入其导向装置,并检查反作用摩擦力是否不足以阻止杆组控制组件的运动。我们在本文中介绍了一种数值方法,用于数值模拟杆簇控制组件插入或插入到其导向装置中(不连续和连续导向装置,导向套管)。精心设计了一个数值模型,其中考虑了许多载荷:杆和导向装置之间的流体载荷,重力和摩擦力。将数值结果与从全尺寸结构获得的实验测量值进行比较。观察到计算数据和测量数据之间的良好一致性。数值模型考虑了导轨的可能偏斜。它清楚地表明,当弓形件弯曲时,摩擦力不能忽略。因此,可以通过检查插入测试期间的反作用力来定位故障的导向系统。然后,数值模型可以帮助决策者在不同的杆组/燃料组件部件之间做出选择。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2007年第6期|p.600-606|共7页
  • 作者单位

    Electricite de France, Research and Development Division, 1, avenue du General de Gaulle, 92141 Claman, France;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;
  • 关键词

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