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UO_2(NO_3)_2-TcO_4^--HNO_3-H_2O/TBP-OK体系萃取过程中锝分配比数学模型研究 被引量:1

Simulation of Technetium Extraction Behavior in UO_2(NO_3)_2-TcO_4^--HNO_3-H_2O/TBP-Kerosene System
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摘要 通过文献报道的锝分配比实验数据与计算结果的分析和对比,引入校正函数P(c0(U),t)对现有锝分配比模型进行改进,建立了UO2(NO3)2-TcO4--HNO3-H2O/TBP-OK萃取体系中锝的数学模型,并编写了锝分配比计算程序。利用国内外相关文献报道的179组实验数据对该程序进行验证,符合情况良好。通过与锝分配比文献数据以及原模型计算结果对比,对改进后锝分配比模型的性能进行了评估,改进结果明显优于原模型。改进后的模型可作为UO2(NO3)2-TcO4--HNO3-H2O/TBP-OK体系、10~60℃、U浓度0~280g/L、硝酸浓度0.1~5mol/L范围内锝和铀萃取行为计算机模拟的基础。 By comparing and analyzing lots of reported data of technetium with the com- puting results, a modification function P(C^° (U) ,t) was introduced to the existing distri- bution coefficient model of technetium, and a new mathematical model for simulating technetium extraction behavior in the system of UO2 (NO3)2-TcO4^-HNO3-H2O/TBP- kerosene was established, as well as a computer program. The reliability of the program was verified by 179 sets of distribution coefficient data, and the results were found to agree well with experimental data. By comparing the reported data of technetium with the computing results, an evaluation was made to test the performance of the revised model. It turned out that the calculation results of the new model were more reliable than that of the one reported previously. The revised model and program can be the foundation to simulating technetium extraction behavior in the system of UO2 (NO3)2- TcOi-HNO3-H2O/TBP-kerosene with the temperature scope from 10 to 60 ℃, U con- centration from 0 to 280 g/L, and nitric acid concentration from 0.1 to 5 mol/L.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2012年第2期160-164,共5页 Atomic Energy Science and Technology
关键词 萃取 数学模型 C (programming language) Computer simulation Extraction Kerosene Mathematical models Nitric acid
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参考文献12

  • 1PRUETT D J.The solvent extraction of hepta-valent technetium by tributyl phosphate[J].SepSci Technol,1981,16(9):1 157-1 179.
  • 2GARRAWAY J,WILSON P D.Coextraction of per-technetium and zirconium by tri-n-butyl phosphate[J].J Less-Common Met,1985,106(2):183-192.
  • 3THOMAE H,SIDDAL L.Behavior of techneti-um in the Purex process,DP-364[R].UK:Sa-vannah River Lab,1969.
  • 4KOLARIK Z,DRESSLER P.Extraction and co-extraction of Tc(Ⅶ),Zr(Ⅳ),Np(Ⅳ,Ⅵ),Pa(Ⅴ)and Nb(Ⅴ)with TBP from nitric acidsolutions[J].Solvent Extraction and Ion Ex-change,1989,7(4):625-644.
  • 5JASSIM T N,LILJENZIN J O,LUNDQVISTR,et al.Coextraction of uranium and technetiumin TBP systems[J].Solvent Extraction and IonExchange,1984,2(3):405-419.
  • 6GARRAWAY J,WILSON P D.The technetium-catalysed oxidation of hydrazine by nitric acid[J].JLess-Common Met,1984,97(2):191-203.
  • 7PRUETT D J.The solvent extraction of hepta-valent technetium and rhenium by tributyl phos-phate,ORNL-8668[R].US:ORNL,1984.
  • 8TACHIMORI S.EXTRA M:A computing codesystem for analysis of the Purex process withmixer settlers for reprocessing,JAERI 1331[R].Japan:JAERI,1994.
  • 9TSUBATA Y,ASAKURA T,MORITA Y.Development of a computer code,PARC,forsimulation of liquid-liquid extraction process inreprocessing,JAEA-Data/Code[R].Japan:JAEA,2008.
  • 10ASAKURA T,HOTOKU S,BAN Y,et al.Technetium separation for future reprocessing[J].Journal of Nuclear and Radiochemical Sci-ences,2005,6(3):271-274.

二级参考文献2

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同被引文献7

  • 1Matsumoto S, Uchiyama G, Ozawa M, et al. Research Committee on Ruthenium and Technetium Chemistry in PUREX System, Organized by the Atomic Energy Society of Japan[J]. Radiochem, 2003, 45(3): 219-224.
  • 2Garraway J, Wilson P D. The Technetium-Catal- ysed Oxidation of Hydrazine by Nitric Acid[J] . J Less-Common Met, 1984, 97: 191-203.
  • 3Lieser K H, Singh R N. Numerical Equations for the Extraction of Tc( VIII ) by Tri-n-Butyl-Phosphate (TBP)[J]. Radiuchim Acta, 1983, 32: 203-206.
  • 4Kanellakopulos B, Konig C P. On the Extraction Behavior of Technetium With Respect to the Purex Process[J]. Radiochlm Acta, 1983, 33 :169-175.
  • 5何辉,李高亮,陈辉,蒋德祥,唐洪彬.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. 被引量:14
  • 6张丕禄,齐占顺,朱志瑄.PUREX流程中Tc(Ⅶ)对U(Ⅳ)反萃Pu(Ⅳ)的影响[J].核化学与放射化学,1999,21(4):219-227. 被引量:7
  • 7田保生,孙玉珍,欧阳应根,李卫民,李瑞雪,郭建华,黄美德,常利,陈永清,罗隆俊.乏燃料后处理洗涤槽中锝的走向控制研究[J].原子能科学技术,2001,35(B05):22-26. 被引量:2

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