ADU湿法制备核燃料含氨放射性废水蒸馏法除氨及回收研究
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- 英文论文题名：Removal and recovery of ammonia by distillation from ammonia-containing radiate waste water produced by ADU wet process for nuclear fuel
- 论文作者：张嘉 ; 康武 ; 刘小龙 ; 刘锦洪
- 英文论文作者：ZHANG Jia ; KANG Wu ; LIU Xiao-long ; LIU Jin-hong ; Nuclear Power Institute of China
- 年：2015
- 作者机构：中国核动力研究设计院四所;
- 论文关键词：氨 ; 去除 ; 回收 ; 蒸馏
- 英文论文关键词：ammonia ; removal ; recovery ; distillation
- 会议召开时间：2015-09-21
- 会议录名称：中国核科学技术进展报告（第四卷）——中国核学会2015年学术年会论文集第6册（核化学与放射化学分卷、核化工分卷）
- 语种：中文
- 分类号：TL941.1
- 学会代码：EGVD
- 会议名称：中国核学会2015年学术年会
- 会议地点：中国四川绵阳
- 主办单位：中国核学会
- 学会名称：中国核学会
- 页数：7
- 文件大小：287k
- 原文格式：O
- 会议级别：全国
摘要
ADU湿法制备核燃料过程中会产生大量含氟含氨沉淀母液。对于该放射性含氨废液的处理,除氟工艺已是比较成熟的技术,但是针对其中氨的工业化去除和回收尚未见文献报道。针对某次生产项目中产生的大量氨含量为20~30 g/L的含氨放射性废液,采用湍球塔微正压蒸馏工艺对氨进行平衡蒸馏,再利用降膜吸收塔和尾气吸收塔的循环吸收液对含氨蒸气进行二级吸收。研究了加热段蒸气流量;湍球塔塔顶温度、平衡段蒸气流量、进料温度及流量、吸收塔循环吸收液流量对氨去除及回收率的影响。通过理论分析计算及实验,最终确定最佳工艺参数和操作条件:平衡段蒸气流量/进料流量:2.5;塔顶温度:75℃~80℃;吸收液循环流量:3 000 L/h时,氨去除率约为80%~85%,回收率在63%~66%,均较为稳定。
The preparation process of nuclear fuel produced large amount of fluorine and ammoniacontaining radiate waste water.Treatment situation for this radiate waste water is that fluoride removal is relatively mature technique,But for the ammonia removal and recycling documents have not been reported.For the fluorine and ammonia-containing waste water whose Ammonia content is about 20~30 g/L in this producing project,use slightly positive pressure distillation process in turbulent ball tower for recovering gas absorber's circular fluid to ammonia secondary absorption.Study the impact of the stream flow of heating section,temperature on top of turbulent ball tower,stream flow of balancing segment,feed temperature and flow and circulating absorption liquid flow of absorption tower to removal and recovery process.Through theoretical analysis and experiment to determine the optimum process parameters and operating conditions:steam flow of balancing segment/feed flow:2.5;temperature on top of turbulent ball tower:75~80 ℃;circulating absorption liquid flow:3 000 L/h.Under these parameters and conditions,the removal rate of ammonia is about 80%~85%,the recovery rate of ammonia is about 63%~66%,both are relatively stable.
The preparation process of nuclear fuel produced large amount of fluorine and ammoniacontaining radiate waste water.Treatment situation for this radiate waste water is that fluoride removal is relatively mature technique,But for the ammonia removal and recycling documents have not been reported.For the fluorine and ammonia-containing waste water whose Ammonia content is about 20~30 g/L in this producing project,use slightly positive pressure distillation process in turbulent ball tower for recovering gas absorber's circular fluid to ammonia secondary absorption.Study the impact of the stream flow of heating section,temperature on top of turbulent ball tower,stream flow of balancing segment,feed temperature and flow and circulating absorption liquid flow of absorption tower to removal and recovery process.Through theoretical analysis and experiment to determine the optimum process parameters and operating conditions:steam flow of balancing segment/feed flow:2.5;temperature on top of turbulent ball tower:75~80 ℃;circulating absorption liquid flow:3 000 L/h.Under these parameters and conditions,the removal rate of ammonia is about 80%~85%,the recovery rate of ammonia is about 63%~66%,both are relatively stable.
引文
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