کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
299311 | 511829 | 2006 | 12 صفحه PDF | دانلود رایگان |

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 + B2O3 at ≅1400 K, representing the corium melt mixture of UO2 + ZrO2.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.
Journal: Nuclear Engineering and Design - Volume 236, Issues 19–21, October 2006, Pages 2199–2210