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Corium crust strength measurements

机译:皮质结皮强度测量

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Corium strength is of interest in the context of a severe reactor accident in which molten core material melts through the reactor vessel and collects on the containment basemat. Some accident management strategies involve pouring water over the melt to solidify it and halt corium/concrete interactions. The effectiveness of this method could be influenced by the strength of the corium crust at the interface between the melt and coolant. A strong, coherent crust anchored to the containment walls could allow the yet-molten corium to fall away from the crust as it erodes the basemat, thereby thermally decoupling the melt from the coolant and sharply reducing the cooling rate. This paper presents a diverse collection of measurements of the mechanical strength of corium. The data is based on load tests of corium samples in three different contexts: (1) small blocks cut from the debris of the large-scale MACE experiments, (2) 30 cm-diameter, 75 kg ingots produced by SSWICS quench tests, and (3) high temperature crusts loaded during large-scale corium/concrete interaction (CCl) tests. In every case the corium consisted of varying proportions of UO_2, ZrO_2, and the constituents of concrete to represent a LWR melt at different stages of a molten core/concrete interaction. The collection of data was used to assess the strength and stability of an anchored, plant-scale crust. The results indicate that such a crust is likely to be too weak to support itself above the melt. It is therefore improbable that an anchored crust configuration could persist and the melt become thermally decoupled from the water layer to restrict cooling and prolong an attack of the reactor cavity concrete.
机译:在严重的反应堆事故中,熔芯材料通过反应堆容器熔化并聚集在安全壳底垫上时,钙的强度是很重要的。一些事故管理策略涉及将水倒在熔体上以使其凝固并阻止皮质/混凝土相互作用。该方法的有效性可能受到熔体和冷却剂之间界面处的硬皮强度的影响。锚定在安全壳壁上的坚固,结实的外壳可能会使尚未熔化的皮质腐蚀外壳,从而腐蚀外壳,从而使熔体从冷却剂中热分离出来,并急剧降低冷却速率。本文介绍了多种测量皮质机械强度的方法。数据基于在三种不同情况下对皮质样品进行的负载测试:(1)从大型MACE实验的碎片中切出的小块;(2)直径30厘米,通过SSWICS淬火测试生产的75公斤铸锭;以及(3)大型皮/混凝土相互作用(CCl)测试期间加载的高温硬皮。在每种情况下,真皮均由不同比例的UO_2,ZrO_2和混凝土成分组成,这些成分代表了在熔融核/混凝土相互作用的不同阶段的轻水堆熔体。数据的收集用于评估锚定的工厂规模的结皮的强度和稳定性。结果表明,这种地壳可能太弱而无法将自身支撑在熔体上方。因此,不可能维持锚固的外壳结构并且使熔体与水层热分离以限制冷却并延长反应堆空腔混凝土的侵蚀。

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