Purex流程萃取体系下Ru的分配比测定及数学模型研究
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- 英文论文题名：The Study on the Distribution model of some components in Purex I The distribution measure and the mathematic model of Ru
- 论文作者：李峰峰 ; 陈延鑫 ; 何辉 ; 肖松涛 ; 李瑞雪 ; 唐洪彬
- 英文论文作者：LI Feng-feng ; CHEN Yan-xin ; HE Hui ; XIAO Song-tao ; LI Rui-xue ; TANG Hong-bin ; Department of Radiochemistry ; China Institute of Atomic Energy
- 年：2015
- 作者机构：中国原子能科学研究院放射化学研究所;
- 论文关键词：Ru ; 分配比 ; 数学模型
- 英文论文关键词：ru ; distribution ratio ; mathematical model
- 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：TL24
- 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：5
- 文件大小：231k
- 原文格式：O
- 会议级别：全国
摘要
通过Ru的分配比实验考察了Ru的分配比随硝酸浓度、温度、萃取时间和Ru自身浓度的变化情况,实验结果表明,Ru分配比随硝酸浓度和温度的升高而降低,随萃取时间延长而升高,Ru自身浓度的大小对Ru分配比的影响较小,在Purex流程工艺条件下,可认为Ru自身浓度对Ru的分配比无影响。同时,在Matlab软件平台上,对实验得到的分配比数据进行了拟合,得到的Ru分配比模型函数公式为D_(Ro_=exp(-0.26·C_H~2+C_H-3.64+0.29·lnEt)·fTBP~2,模型函数适用范围为0.3mol/L~5.0mol/L HNO_3的萃取体系。
The distribution of Ru change with HNO_3 concentration,temperature,extraction time and Ru concentration has been studied by experiment,the results are that the distribution of Ru decreases with the increase of HNO_3 and tempeture,increases with the prolong time of extraction,is little influenced by Ru concentration especially in Purex conditions.Meanwhile,the distribution model of Ru has been fit in Matlab software,the equation of Ru distribution model is D_(Ru) = exp(-0.26 · C_H~2+C_H-3.64 + 0.29 · lnEt) · fTBP~2,the equation can be used in the HNO_3 concentration range of 0.3mol/L to 5 mol/L.
The distribution of Ru change with HNO_3 concentration,temperature,extraction time and Ru concentration has been studied by experiment,the results are that the distribution of Ru decreases with the increase of HNO_3 and tempeture,increases with the prolong time of extraction,is little influenced by Ru concentration especially in Purex conditions.Meanwhile,the distribution model of Ru has been fit in Matlab software,the equation of Ru distribution model is D_(Ru) = exp(-0.26 · C_H~2+C_H-3.64 + 0.29 · lnEt) · fTBP~2,the equation can be used in the HNO_3 concentration range of 0.3mol/L to 5 mol/L.
引文
[1]W.W.Schuiz,L.L.Burger,J.D.Navratil.Science and Technology of Tributyl Phosphate VolumeⅢ,Applications of Tributyl Phosphate in Nuclear Fuel Processing[M].USA:CRC Press,Inc.1990.
[2]林灿生.裂变产物元素过程化学[M].北京:中国原子能出版社,2012.Lin Cansheng.The process chemistry of fission products[M].Beijing:China Atomic press.2012.
[3]Leon Maya.Ruthenium(Ⅳ)in Nitric Acid Media[J].J.Inorg.Nucl.Chem,1979,41:67-71.
[4]肖松涛,罗方祥,杨贺等.微量钌在Pu纯化循环中的行为[J].核化学与放射化学,2013,35(3):144-150.Xiao Song-tao,Luo Fang-xiang,Yang He,et al.Behavior of Trace Ruthenium in Plutonium Purification Cycle[J].Journal of Nuclear and Radiochemistry,2013,35(3):144-150.
[5]Eichholz G.G.Hazards and Control of Ru in the Nuclear Fuel Cycle[J].Progress in Nuclear Energy,1978,2:29-76.
[6]D.J.Pruett.The Solvent Extraction Behavior of Ruthenium I-The Nitric Acid-Tri-n-Butyl Phosphate[J].Radiochimica Acta,1980,27(2):115-120.
[7]何辉,李高亮,陈辉等.Purex流程共去污工艺计算机稳态模拟[J].原子能科学技术,2008,42(9):784-789.HeHui,Li Gao-liang,ChenHui,et al.Computer simulation of Co-decontamination Process in Purex[J].Atomic Energy Science and Technology,2008,42(9):784-789.
[8]常利,欧阳应根,张洁萍等.Purex流程的改进Ⅰ.共去污单元锆、钌净化工艺[J].核化学与放射化学,2013,35(2):87-91.Chang Li,Ouyang Ying-gen,Zhang Jie-ping,et al.Improvement of the Purex Process[J].Journal of Nuclear and Radiochemistry,2013,35(2):87-91.(In Chinese)
[9]Yasuhiro Tsubata,Toshihide Asakura and Yasuji Morita.Development of a Computer Code,PARC,for Simulation of Liquid-Liquid Extraction Process in Reprocessing[R].JAEA-2008-010,2008.
[2]林灿生.裂变产物元素过程化学[M].北京:中国原子能出版社,2012.Lin Cansheng.The process chemistry of fission products[M].Beijing:China Atomic press.2012.
[3]Leon Maya.Ruthenium(Ⅳ)in Nitric Acid Media[J].J.Inorg.Nucl.Chem,1979,41:67-71.
[4]肖松涛,罗方祥,杨贺等.微量钌在Pu纯化循环中的行为[J].核化学与放射化学,2013,35(3):144-150.Xiao Song-tao,Luo Fang-xiang,Yang He,et al.Behavior of Trace Ruthenium in Plutonium Purification Cycle[J].Journal of Nuclear and Radiochemistry,2013,35(3):144-150.
[5]Eichholz G.G.Hazards and Control of Ru in the Nuclear Fuel Cycle[J].Progress in Nuclear Energy,1978,2:29-76.
[6]D.J.Pruett.The Solvent Extraction Behavior of Ruthenium I-The Nitric Acid-Tri-n-Butyl Phosphate[J].Radiochimica Acta,1980,27(2):115-120.
[7]何辉,李高亮,陈辉等.Purex流程共去污工艺计算机稳态模拟[J].原子能科学技术,2008,42(9):784-789.HeHui,Li Gao-liang,ChenHui,et al.Computer simulation of Co-decontamination Process in Purex[J].Atomic Energy Science and Technology,2008,42(9):784-789.
[8]常利,欧阳应根,张洁萍等.Purex流程的改进Ⅰ.共去污单元锆、钌净化工艺[J].核化学与放射化学,2013,35(2):87-91.Chang Li,Ouyang Ying-gen,Zhang Jie-ping,et al.Improvement of the Purex Process[J].Journal of Nuclear and Radiochemistry,2013,35(2):87-91.(In Chinese)
[9]Yasuhiro Tsubata,Toshihide Asakura and Yasuji Morita.Development of a Computer Code,PARC,for Simulation of Liquid-Liquid Extraction Process in Reprocessing[R].JAEA-2008-010,2008.