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A NEW EXPERIMENTAL RD PROGRAM ASSOCIATED WITH THE CORIUM JET IMPINGEMENT ON THE ASTRID CORE CATCHER SACRIFICIAL MATERIAL

机译:一种与Astrid Core Catcher牺牲材料上的叉子冲击相关的新实验研发程序

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The strategy used in ASTRID Sodium Fast Reactor Demonstrator to mitigate the consequences of a postulated severe accident relies on the presence of dedicated corium discharge tubes between the active core region and the lower plenum and an in-vessel core catcher in the lower plenum to collect and cool the molten fuel. In this situation, the corium progression from the core towards the core catcher could lead to jet impingement on the core catcher surface and a subsequent degradation of the core-catcher material(s). After a review of the existing experimental database, it appeared necessary to define a dedicated experimental R&D program related to the long-lasting jet impingement on thick material plates. A particular behaviour will be studied when a molten pool is created (named "pool effect") at the impingement point that reduces the heat transfer at the jet-material interface. In this scope, experimental tests with simulants and prototypic materials will be carried out by using the most possible representative conditions (e.g. Reynolds and Prandtl numbers) for ESFR (European Sodium Fast Reactor) severe accident conditions. Three R&D program have been proposed: (i) Ice-water jet impingement, the few results in the literature show a good agreement between ice-water jet system and metal wall/metal jet system which justifies the use of such simulant materials for investigating the impingement behaviour. The JOLO facility will be designed at LEMTA Nancy University. (ii) Molten steel jet impingement on the thick wall. The MOCKA facility in the Karlsruhe Institute of Technology will be used. (iii) Dedicated test section PLINIUS-2 IMPACT will be designed in future PLINIUS 2 large-mass prototypic-corium experimental platform at CEA Cadarache. First experiments have been carried out in the JOLO facility and provided dynamic ablation data before and during the formation of the pool. Additional JOLO tests and the MOCKA tests will be carried out in the frame of the ESFR-SMART European project starting by the end of 2017. The MOCKA tests will be perfoimed with steel at higher temperature than in JOLO, before running core catcher qualification tests with prototypical corium (depleted U02 and steel) and the ASTRID core catcher selected materials in PLINIUS-2 platform. New correlations and models will be developed from the experimental results in order to estimate the heat transfer data between the jet and the impacted material taking into account the "pool effect" phenomenon.
机译:Astrid快速反应器示范器中使用的策略减轻假设的严重事故的后果依赖于活性核心区域和下层间的专用芯管排放管和下部增压室中的血管内芯捕集器来收集和冷却钢化燃料。在这种情况下,从芯捕获器的芯进程可能导致芯捕机表面的喷射冲击和随后的芯捕手材料的降解。在审查现有的实验数据库之后,似乎有必要定义与厚材料板上的长持久喷射冲击相关的专用实验研发程序。在将熔池被创建(名为“池效果”)处的冲击点时将研究特定行为,该挖掘点降低喷射材料界面的热传递。在该范围中,将通过使用最可能的代表性条件(例如Reynolds和Prandtl号码)进行模拟剂和原型材料的实验测试,用于ESFR(欧洲钠快速反应堆)严重事故条件。已经提出了三个研发计划:(i)冰水喷射冲击,文献的少数结果表明了冰水喷射系统和金属壁/金属喷射系统之间的良好一致性,这使得使用这种模拟材料来研究这些模拟材料冲击行为。 JOLO设施将在Lemta Nancy大学设计。 (ii)厚壁上的钢水喷射冲击。将使用Karlsruhe技术研究所的Mocka设施。 (iii)专用测试部分Plinius-2将在Cea Cadarache的未来Plinius 2大型原型 - 辅助实验平台中设计。首次实验已经在JOLO设施中进行,并在池的形成之前和期间提供了动态消融数据。额外的JOLO测试和Mocka测试将在2017年底开始的ESFR-Smart欧洲项目的框架中进行。在运行核心捕集器资格测试之前,Mocka测试将在较高的温度下在较高的温度下用钢水升温原型核心(耗尽U02和钢)和普里尼斯-2平台中的Astrid核心捕集器选定的材料。将从实验结果中开发新的相关性和模型,以估计喷射和受冲击材料之间的传热数据,以考虑“池效应”现象。

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