首页> 外文会议>International Nuclear Fuel Cycle Conference >PROGRESS IN REAL-TIME MONITORING FOR CONTROLLING THE COMPOSITION OF THE URANIUMPLUTONIUM NITRATE PRODUCT IN A TRI-BUTYL PHOSPHATE BASED FLOWSHEET
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PROGRESS IN REAL-TIME MONITORING FOR CONTROLLING THE COMPOSITION OF THE URANIUMPLUTONIUM NITRATE PRODUCT IN A TRI-BUTYL PHOSPHATE BASED FLOWSHEET

机译:在基于三丁基磷酸盐的流线中控制铀戊二铵产物组成的实时监测进展

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Nuclear fuel recycling flowsheets that do not fullyseparate plutonium (Pu) from uranium (U) are of interestdue to reduction in the Pu attractiveness level, and thepotential to simplify the manufacturing of mixed oxidefuel. Our research in this regard has not been directed atdevelopment or testing of a particular flowsheet forindustrial application, but rather at examining how well aparticular U/Pu mass ratio (chosen to be 7/3 for thisproject) can be maintained using laboratory-scalecounter-current solvent extraction equipment (2-cmcentrifugal contactors). Integral to this effort is thedeployment of real-time optical spectroscopic tools tomonitor the U/Pu ratio in the product stream, so thatadjustments to process parameters can be made toachieve and maintain the targeted U/Pu ratio.In the co-decontamination (CoDCon) flowsheettested in this work, the co-extraction of U and Pu followsstandard protocol for a tri-butyl phosphate (TBP) basedflowsheet. The Pu is stripped from the solvent usingU(Ⅳ). The control point for adjusting the U/Pu ratio isthe flowrate of a TBP solvent stream used to extract U(Ⅳ)from the aqueous phase in the Pu stripping contactorbank. In a conventional recycling operation, the flowrateof this TBP solvent stream would be sufficiently high toquantitatively extract the U(Ⅳ) so that a pure Pu productis obtained. However, as the flowrate of this stream isdecreased, the amount of U(Ⅳ) remaining in the aqueousphase (i.e., with the Pu) increases. The novel aspect ofour approach is the real-time monitoring of the U/Puratio in the U/Pu product stream using opticalspectroscopy coupled with chemometric modeling. Thisreal-time feedback allows adjustment of the TBP solventflowrate to achieve the target U/Pu ratio.Several runs of the flowsheet have been conductedusing simulated dissolved fuel solutions. Monitoring andcontrol of the U/Pu ratio has been demonstrated in allcases. Once steady-state is reached, very stable control ofthe U/Pu ratio can be achieved. Our observations are thatthe uncertainties in the final U/Pu product are dominatedby the uncertainties in the analytical methods used toanalyze the product obtained, rather than in operation ofthe solvent extraction equipment.
机译:核燃料回收流量不完全来自铀(U)的单独的钚(PU)是感兴趣的由于PU吸引力降低,以及潜力简化混合氧化物的制造燃料。我们在这方面的研究尚未指示对特定流程表的开发或测试工业应用,而是在检查一个人特定U / PU质量比(选择为7/3项目)可以使用实验室规模维护反电流溶剂萃取设备(2厘米离心接触器)。这项努力的一体化是部署实时光学光谱工具监视产品流中的U / PU比,这样可以进行处理参数的调整实现并保持目标U / PU比率。在共同净化(Codcon)流程中在这项工作中进行了测试,U和PU的共同提取遵循基于三 - 磷酸三丁酯(TBP)的标准方案流程图。 PU从溶剂中剥离使用u(ⅳ)。调整U / PU比的控制点是用于提取U(ⅳ)的TBP溶剂流的流量从PU汽提器中的水相银行。在传统的再循环操作中,流量这种Tbp溶剂流是足够高的定量提取U(ⅳ),以便纯PU产品得到了。但是,随着该流的流量是减少,剩余在水中的U(Ⅵ)的量相(即,PU)增加。新颖方面我们的方法是U / PU的实时监测使用光学U / PU产品流中的比率光谱学与化学计量建模耦合。这个实时反馈允许调节TBP溶剂流量以实现目标U / PU比率。已经进行了几次流行的流程图使用模拟溶解燃料溶液。监控和已经证明了对U / PU比的控制案件。一旦达到稳态,控制非常稳定可以实现U / PU比率。我们的观察是最终U / PU产品中的不确定性占主导地位通过用于分析方法的不确定性分析所获得的产品,而不是在运行中溶剂萃取设备。

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