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An Empirical Np Solubility Model Based on Spent Fuel Dissolution Experiments

机译:基于乏燃料溶解实验的经验Np溶解度模型

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In TSPA-VA, based on the concept that Np release isrncontrolled by secondary uranium minerals a mechanisticrnmodel of Np release from spent fuel dissolution has beenrndeveloped by the author using the reactive-transport codernAREST-CT. The AREST-CT model yields a lower Nprnsolubility, and which in turn generates a lower dose rate.rnBy examining spent fuel dissolution data, this paper furtherrnexplores the secondary uranium mineral concept and anrnempirical model is proposed. This model gives a veryrnsimilar Np solubility range as given by the AREST-CTrnmodel. As a matter of fact, this empirical model and thernAREST-CT model complement to each other.
机译:在TSPA-VA中,基于由次生铀矿物控制Np释放的概念,作者使用反应性运输代码AREST-CT开发了从乏燃料溶解中释放Np的机理模型。 AREST-CT模型产生的Npr溶解度较低,从而产生较低的剂量率。通过检查乏燃料的溶解数据,本文进一步探讨了次生铀矿物概念并提出了经验模型。该模型给出了与AREST-CTrn模型相同的Np溶解度范围。实际上,该经验模型和rnAREST-CT模型是相辅相成的。

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