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Analysis of the influence of the thermalhydraulic to neutronic mapping in the RIA analysis in Almaraz NPP

机译:在Almaraz核电厂的RIA分析中分析热工液压对中子图的影响

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The present work consists of the study of the influence of different definitions of the thermalhydraulic model in a REA analysis at Almaraz NPP using RELAP5/PARCS v2.7 coupled code. A series of calculations with different number of thermalhydraulic channels to represent the core has been made. These channels have been coupled to the neutronic model, developed in a one-to-one basis, that is, each fuel assembly is represented by a radial node in PARCS v2.7 code. The mapping between the thermalhydraulic and the neutronic model has been performed in different ways to study its influence in the 3D results. This study contributes to obtain more accurate results in the REA analysis in Almaraz NPP.
机译:本工作包括在Almaraz NPP的REA分析中使用RELAP5 / PARCS v2.7耦合代码对热工水力模型的不同定义的影响进行研究。进行了一系列使用不同数量的热液通道来表示岩心的计算。这些通道已与以一对一方式开发的中子学模型耦合,也就是说,每个燃料组件均由PARCS v2.7代码中的径向节点表示。热工液压模型与中子模型之间的映射已通过不同的方式进行了研究,以研究其对3D结果的影响。这项研究有助于在Almaraz NPP的REA分析中获得更准确的结果。

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