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Radiological characterization of the reactor pressure vessel of Trino NPP for dismantling purposes

机译:Trino NPP用于拆卸目的反应堆压力容器的放射学表征

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摘要

The decommissioning of a Nuclear Power Plant (NPP1) is based on the knowledge of radioactivity content and its distribution. The reactor pressure vessel and its internal components have the highest radioactive levels in the plant, considering the contributions of the residual radioactivity due to neutron activation and the surface contamination. This paper presents the steps of the radiological characterization process carried out on the pressure vessel and internals of "Enrico Fermi" NPP. The activation data, computed by analytical procedures in a previous study, are analysed and semi-empirical models have been developed to determine contamination levels where activation is not expected. Non-invasive external dose rate measurements have been performed for a preliminary validation of the activation profiles and to be used in the contamination models. Afterwards, an optimal sampling plan has been adopted to quantitatively validate the current radiological framework 30 years after the end of the lifecycle, in order to get the radiological classification for the optimal choice of the cutting techniques and of the number of radioactive waste containers.
机译:核电厂(NPP1)的退役是基于放射性含量及其分布的知识。考虑到由于中子活化和表面污染引起的残留放射性的贡献,反应堆压力容器及其内部组件在工厂中具有最高的放射性水平。本文介绍了在“ Enrico Fermi” NPP的压力容器和内部进行的放射学表征过程的步骤。将对通过先前研究中的分析程序计算出的活化数据进行分析,并开发了半经验模型来确定预期不会活化的污染水平。已经进行了非侵入性外部剂量率测量,以初步验证激活曲线,并将其用于污染模型。此后,采用了最佳采样计划,以在生命周期结束30年后对当前的放射学框架进行定量验证,以便获得放射学分类,从而对切割技术和放射性废物容器的数量进行最佳选择。

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