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EXPERIMENTAL INVESTIGATIONS ON THE COOLABILITY OF DEBRIS BEDS UNDER VARIATION OF INFLOW CONDITIONS

机译:入流条件变化下泥石床可塑性的实验研究

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In case of a severe accident, continuous unavailability of cooling water to the reactor core may result in over heating of the fuel elements and the loss of core integrity. Under such conditions, the molten core can relocate to the lower plenum of the reactor pressure vessel (RPV) and form a structure of heated particles of different sizes and shapes (debris) due to the possible presence of residual water. To avoid a remelting and in the further course of the accident a damage to the RPV it is of great importance to establish long-term coolability. If long-term coolability cannot be established a failure of the RPV and uncontrolled melt release would be the consequence. In this case for certain reactor types again a debris bed can be formed in the reactor cavity. The DEBRIS test facility at IKE was established to investigate the coolability limits of such debris beds. The cylindrical bed (150 mm diameter, 640 mm height) is heated by an inductive heating system, which acts as a volumetric heat source. To investigate the thermohydraulic debris bed behavior the test section is equipped with 55 thermocouples and 8 differential pressure transducers. The maximum removable heat flux (dryout heat flux, DHF) from a debris bed can be determined by increasing the heat input in small increments. This paper presents mainly the results of systematic boiling and dryout experiments at IKE. In contrast to IKE experiments in the past the focus is on debris beds consisting of non-spherical particles with well-defined geometries such as cylinders and screws to investigate the influence of the particle shape on the bed's coolability. For the current set of experiments, the cooling behavior of two kinds of particles was investigated under variation of system pressure (0.1, 0.3 and 0.5 MPa) and inflow condition. The debris bed was flooded either from top or simultaneously from top and from bottom by a natural circulation loop. Additionally, several downcomer configurations were investigated. The experimental results show that a downcomer can significantly improve the bed's coolability since the penetration of water into the bed is not limited by the counter-current flow limitation (CCFL).
机译:在发生严重事故的情况下,反应堆堆芯持续无法获得冷却水可能会导致燃料元件过热并损失堆芯完整性。在这样的条件下,由于可能存在残留水,熔融核可移至反应堆压力容器(RPV)的下部气室,并形成具有不同尺寸和形状(碎屑)的加热颗粒的结构。为了避免重熔以及在事故的后续过程中损坏RPV,建立长期可冷却性非常重要。如果无法建立长期的可冷却性,则将导致RPV失效并导致熔体释放不受控制。在这种情况下,对于某些反应器类型,可以在反应器腔室中再次形成碎屑床。建立了IKE的DEBRIS测试设施,以研究此类碎屑床的可冷却性极限。圆柱形床(直径150毫米,高度640毫米)由感应加热系统加热,该系统用作体积热源。为了研究热工液压碎屑床的性能,测试部分配备了55个热电偶和8个压差传感器。可以通过以较小的增量增加热量输入来确定来自碎屑床的最大可移动热通量(干燥热通量,DHF)。本文主要介绍了IKE系统沸腾和干透实验的结果。与过去的IKE实验相反,重点是由具有非限定几何形状的非球形颗粒(例如圆柱体和螺钉)组成的碎片床,以研究颗粒形状对床的可冷却性的影响。对于当前的一组实验,研究了两种颗粒在系统压力(0.1、0.3和0.5 MPa)和流入条件变化下的冷却行为。通过自然循环回路从顶部或同时从顶部和底部淹没碎片床。另外,研究了几种降液管配置。实验结果表明,降水管可以显着改善床的可冷却性,因为水进入床的渗透不受逆流流量限制(CCFL)的限制。

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