首页> 美国政府科技报告 >AN IMPROVED AQUEOUS PROCESS FOR ZIRCONIUM ALLOY NUCLEAR REACTOR FUELS PARTⅠ. PRELIMINARY LABORATORY STUDIES
【24h】

AN IMPROVED AQUEOUS PROCESS FOR ZIRCONIUM ALLOY NUCLEAR REACTOR FUELS PARTⅠ. PRELIMINARY LABORATORY STUDIES

机译:一种改进的锆合金核反应堆燃料的水溶液工艺第一部分。初步实验室研究

获取原文

摘要

The expanding use of Zircaloy-clad zirconium-enriched uranium alloy fuel has suggested a need for higher capacity reprocessing facilities. The most urgent requirement is for continuous dissolution equipment to match the solvent extraction capacity already available at Idaho Chemical Processing Plant. Because of the rapid dissolution rates possible with aqueous hydrofluoric acid on clean metal as well as on oxidized fuels, and subsequent flowsheet economics, it is the reagent of choice.nLaboratory measurements and a survey of the properties of uranium tetrafluoride indicated highest solubility in the dissolver effluent was obtained at higher total fluoride concentrations and lower fluoride-to-zirconium mole ratios. Since zirconium salts have been shown to be susceptible to precipitation at higher fluoride and zirconium concen¬trations, an optimum dissolver effluent composition was selected for a Dilute Flowsheet at about 5M total fluoride and a 1.1M zirconium.nThe operation of two bench-scale dissolvers verified the feasibility of a continuous process, and Monel and Carpenter-20(Ob) were confirmed as suitable materials of construction for the dissolver. Using the Dilute Flowsheet, uranium solubility equivalent to the dissolution of fuels containing 2 per cent uranium, over-all, was achieved.nCorrelations of dissolver effluent flow rate with effluent compos¬ition and with total zirconium dissolved are given for guidance in engineering scale-up.

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号