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Experiments on in-vessel melt coolability in the EC-FOREVER Program

机译:EC-FOREVER计划中的船内熔体冷却性实验

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摘要

This paper reports the results from the experiments conducted on the coolability of corium melt during a severe accident scenario when the bottom head is full of the core melt, undergoing natural circulation. These experiments are part of the EC-FOREVER Program in which vessel failure experiments have also been performed. The experiments are performed in a 1/10th scale vessel (≈400 mm diameter and 15 mm wall thickness) and the oxidic melt employed is the mixture CaO + B_2O_3 at ≈ 1400 K, representing the corium melt mixture of UO_2 + ZrO_2. The experiments employed an initial phase, during which uniform volumetric heating of the melt was provided and the vessel was pressurised to ≈25 bar, for several hours, to generate maximum creep deformation of ≈ 5%, in order to provide the conditions for the formation of a gap between the melt-pool crust and the bottom head wall. After this phase, the vessel was flooded with water. Data were obtained on only the vessel and the melt pool temperatures in one of the EC-FOREVER experiments reported here. In the second experiment, however, besides the temperature data, additional data were obtained on the steam flow rate and the heat transfer to the water, at the upper face of the melt pool, as a function of time. It was found that the gap cooling mechanism was not effective in reducing the vessel wall temperatures after water flooding. Post-test examinations revealed that the water ingression extended to the depth of only ≈60 mm in the melt pool. The character of the heat transfer to the water from the melt pool upper surface was found to be similar to that observed in the MACE tests for the coolability of an ex-vessel melt pool flooded by water at the top.
机译:本文报告了在严重事故情况下,当底部头部充满堆芯熔体并进行自然循环时,发生在严重事故情况下的熔体可冷却性实验的结果。这些实验是EC-FOREVER计划的一部分,其中还进行了容器故障实验。实验是在1/10比例的容器(直径约400 mm,壁厚15 mm)中进行的,所用的氧化熔融物为CaO + B_2O_3的混合物,≈1400 K,代表UO_2 + ZrO_2的皮质熔融混合物。实验采用一个初始阶段,在此阶段中,对熔体进行均匀的体积加热,并将容器加压至≈25bar,持续数小时,以产生最大≈5%的蠕变变形,从而为形成提供条件。熔池外皮和底盖壁之间的缝隙。在该阶段之后,将容器用水淹没。在此处报告的EC-FOREVER实验之一中,仅获得了有关容器和熔池温度的数据。然而,在第二个实验中,除了温度数据外,还获得了有关熔体池上表面的蒸汽流量和向水的热传递随时间变化的其他数据。发现间隙冷却机制在降低注水后不能有效降低容器壁温度。测试后的检查表明,在熔池中,水的浸入扩展到仅≈60毫米的深度。发现从熔池上表面到水的热传递特征与在MACE测试中观察到的顶部被水淹没的前容器熔池的冷却性相似。

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  • 来源
    《Nuclear Engineering and Design》 |2006年第21期|p.2199-2210|共12页
  • 作者单位

    Division of Nuclear Power Safety (NPS), Royal Institute of Technology (KTH), Alba Nova University Center, 10691 Stockholm, Sweden;

  • 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

  • 入库时间 2022-08-18 00:46:59

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