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Experimental Study on Alkali and Alkaline Earth Metal Oxide Solubility in LiCl at 923 K

机译:923 K下LiCl中碱和碱土金属氧化物溶解度的实验研究。

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During the electrolytic reduction of oxide usednuclear fuel in molten LiCl, SrO and Cs_2O are dissolvedinto the molten salt electrolyte. Because 90Sr and 137Cs arehighly heat-generating fission products, the heat load ofthe reduced metallic spent fuel largely decreases.Therefore, the separation of Sr and Cs from the actinidematerial stream will reduce a geological disposal facilityfootprint. It is known that SrO and Cs_2O react with LiCland form SrCl2 and CsCl in LiCl melts, however, thesolubility of these oxides in molten LiCl have not beenproperly studied.The present study investigates the solubility of theLi_2O in LiCl at 923 K, preceding SrO and Cs_2O studies.Samples were taken at equilibrium from the molten LiClsolution in contact with 5, 10, 15 wt.% of Li_2O. Thematerial composition of the samples was analyzed by acidtitration for Li_2O. The measured solubility was alsocompared to the solubility calculated from the opencircuit potential between indicator and referenceelectrode at saturation of Li_2O.
机译:在电解还原过程中使用的氧化物 熔融LiCl中的核燃料,SrO和Cs_2O溶解 进入熔融盐电解质中。因为90Sr和137Cs是 高产裂变产物,热负荷 减少的金属乏燃料大量减少。 因此,从r系元素中分离出Sr和Cs 物质流将减少地质处置设施 脚印。已知SrO和Cs_2O与LiCl反应 并在LiCl中形成SrCl2和CsCl熔化,但是, 这些氧化物在熔融LiCl中的溶解度尚未确定 经过适当研究。 本研究调查了 在进行SrO和Cs_2O研究之前,在923 K的LiCl中存在Li_2O。 在平衡状态下从熔融的LiCl中取样 溶液与5、10、15 wt。%的Li_2O接触。这 用酸分析样品的材料成分 滴定Li_2O。测得的溶解度也为 与从露天计算出的溶解度相比 指示器和参考之间的电路电势 电极在Li_2O饱和时。

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