首页> 外文会议>14th International Conference on Nuclear Engineering(ICONE14) vol.5 >CHARACTERISTICS OF MELTING FOR THE RADIOACTIVE ALUMINUM WASTES FROM THE DECOMMISSIONED NUCLEAR FACILITIES
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CHARACTERISTICS OF MELTING FOR THE RADIOACTIVE ALUMINUM WASTES FROM THE DECOMMISSIONED NUCLEAR FACILITIES

机译:退役核设施中放射性铝废物的熔化特性

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The characteristics of an aluminum melting and the radionuclide distribution have been investigated in a muffle furnace and a lab-scale arc furnace as part of the fundamental research for a melting of the metallic wastes generated by dismantling research reactors. The melting of aluminum was carried out with the use of surrogate nuclides such as cobalt, cesium, and strontium and fluxes such as NaCl-KCl-Na_3AlF_6 (Flux A), NaCl-NaF-KF (Flux B), CaF_2 (Flux C), and LiF-KCl-BaCl_2 (Flux D). The effects of the melting temperature and the type of flux on the melting of the aluminum and the nuclide distribution in the ingot, slag, and dust phase were investigated in a muffle furnace. The addition of the flux increased the fluidity of the aluminum melt, which has a slight difference according to the type of fluxes, and the amounts of the slag generated during the melting with the Flux types B and C were larger than those with flux types A and D. The results of the XRD(X-Ray Diffracto -meter) analysis showed that the surrogate nuclides move into the slag, which can be easily separated from the melt, and then they combine with the aluminum oxide to form a more stable compound. The distribution ratio of the cobalt in the ingot phase was less than 20% according to the type of fluxes. A removal efficiency of more than 99.5% for cesium and strontium from the ingot phase could be achieved. Similar results for the slag formation and the distribution of the surrogate nuclides were obtained in a direct current graphite arc melting system. Therefore, it is expected that a greaterrnpart of the aluminum wastes generated from the retired research reactors can be recycled or their volume reduced to be disposed of by a melting.
机译:在马弗炉和实验室规模的电弧炉中,已经进行了铝熔化和放射性核素分布的研究,这是对拆除研究堆产生的金属废物进行熔化的基础研究的一部分。铝的熔化是使用替代核素(例如钴,铯和锶)和助熔剂(例如NaCl-KCl-Na_3AlF_6(助熔剂A),NaCl-NaF-KF(助熔剂B),CaF_2(助熔剂C)进行的。 ,以及LiF-KCl-BaCl_2(助焊剂D)。在马弗炉中研究了熔化温度和助熔剂类型对铝的熔化以及铸锭,炉渣和粉尘相中核素分布的影响。助熔剂的添加增加了铝熔体的流动性,铝熔体的流动性随助熔剂的类型而略有差异,并且在助熔剂类型B和C的熔化过程中产生的炉渣量大于助熔剂类型A的熔渣量。 XRD(X射线衍射仪)分析的结果表明,替代核素移动到炉渣中,很容易从熔体中分离出来,然后与氧化铝结合形成更稳定的化合物。 。根据焊剂的类型,钴在锭相中的分布比例小于20%。从锭相中除去铯和锶的效率可达到99.5%以上。在直流石墨电弧熔化系统中,炉渣形成和替代核素分布的结果相似。因此,期望从退休的研究反应堆产生的大部分铝废物可以被回收或减少其体积以通过熔融处理。

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