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首页> 外文会议>49th annual meeting on nuclear technology >Development of a monitoring concept for Transport and Storage Containers for Spent Fuel and Heat-Generating High-Level Radioactive Waste on Prolonged Intermediate Storage
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Development of a monitoring concept for Transport and Storage Containers for Spent Fuel and Heat-Generating High-Level Radioactive Waste on Prolonged Intermediate Storage

机译：制定长期中间存储中用过的燃料和产生高放射性废物的运输​​和存储容器的监视概念

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Until the availability of long-term storages in deep geological formations, there is a need in Germany and also in other countries worldwide to store intermediately spent fuel assemblies in a safe way in transport and storage containers which are located inside the nuclear power plants (cf. Fig. 1). The transport and storage containers, which are qualified for the intermediate storage of spent fuel assemblies in Germany, are of the type CASTOR V/19 (PWR fuel assemblies) [1] or CASTOR V/52 (BWR fuel assemblies). At the moment, these containers have a maximum permissible operating time of 40 years. A prolonged intermediate storage of the spent fuel assemblies may exceed this period. It can be ascertained that for the long-term behavior of stored intermediately spent fuel assemblies only few information are available and a detailed modelling of radiochemical and thermomechanical material behavior is challenging. Because of this there is the necessity to evaluate and develop possibilities for long term monitoring of transport and storage containers and the inventory. A cooperative project between the project partners Dresden Technical University (TUD) and Zittau/Görlitz University of Applied Sciences (HSZG) has the goal to evaluate different measurement principles and a suitable monitoring concept for non-invasive long term monitoring of transport and storage containers as well as the container inventory. This paper deals with a brief description of the cooperative project as well as with the development of an approach for a monitoring concept.
机译：在深层地质构造中可以长期存储之前，德国以及世界其他国家/地区都需要以安全的方式将中间乏燃料组件存储在位于核电站内部的运输和存储容器中（参见。 图。1）。在德国，适合于中间存储乏燃料组件的运输和存储容器属于CASTOR V / 19（PWR燃料组件）[1]或CASTOR V / 52（BWR燃料组件）类型。目前，这些容器的最长允许使用时间为40年。乏燃料组件的长时间中间存储可能会超过此期限。可以确定的是，对于所存储的中间用过的燃料组件的长期行为，只有很少的信息可用，并且放射化学和热机械材料行为的详细建模具有挑战性。因此，有必要评估和开发对运输和存储容器以及库存进行长期监控的可能性。项目合作伙伴德累斯顿技术大学（TUD）和齐陶/格尔利茨应用科技大学（HSZG）之间的合作项目旨在评估不同的测量原理和合适的监测概念，以便对运输和储存容器进行无创长期监测，例如以及集装箱库存。本文简要介绍了合作项目以及监视概念方法的发展。

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    Sebastian Schmidt; Daniel Fiß; Sebastian Reinicke; Michael Wagner; Reuven Rachamin; Alexander Kratzsch; Uwe Hampel;

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    Institute of Process Technology, Process Automation and Measuring Technology, Zittau/Görlitz University of Applied Sciences, Zittau, Germany;

    Institute of Process Technology, Process Automation and Measuring Technology, Zittau/Görlitz University of Applied Sciences, Zittau, Germany;

    Institute of Process Technology, Process Automation and Measuring Technology, Zittau/Görlitz University of Applied Sciences, Zittau, Germany;

    AREVA Endowed Chair of Imaging Techniques in Energy and Process Engineering, Dresden Technical University, Dresden, Germany;

    AREVA Endowed Chair of Imaging Techniques in Energy and Process Engineering, Dresden Technical University, Dresden, Germany;

    Institute of Process Technology, Process Automation and Measuring Technology, Zittau/Görlitz University of Applied Sciences, Zittau, Germany;

    AREVA Endowed Chair of Imaging Techniques in Energy and Process Engineering, Dresden Technical University, Dresden, Germany;

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