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International safeguards for a geological repository for the final disposal of spent light water power reactor fuel

机译:最终处置乏水反应堆燃料的地质处置库的国际保障

摘要

The possibility of the direct final disposal of spent fuel elements is considered as an alternative to the commercial reprocessing of fuel elements. Final disposal aims at isolating radioactive material from the biosphere and from possibilities of accidental human access without any time limit. The safety concept is designed to ensure the integrity of the repository without requiring human maintenance or monitaring after the final closure of the repository. Final disposal is conceived of as irreversible disposal. Within the framework of the research and development programme "Alternative Waste Management Techniques" the emplacement of spent fuel elements in a salt dome is being studied. Several concepts have been compiled for conditioning 1 for the final disposal canister and emplacement techniques for this direct final disposal of spent fuel elements. One concept which best fulfills the criteria of safety engineering 1 technical feasibility, availability of raw materials, and also approaches to economic efficiency and nuclear materials safeguards 1 wasselected as a reference in each case. Back-up solutions for each component were also determined over and above establishing the reference concepts. A nuclear materials safeguards concept is to be developed by the KFA-TUG on the basis of the reference concept. This safeguards concept for Alternative Waste Management comprises safeguarding the products for final disposal from their arrival atthe geological repository. Individual aspects important for applying international safeguards measures have been selected and compiled in Chap. 2 from the large volume of information required for this concept and from detailed technical problems already known.[...]
机译:直接最终处理用过的燃料元件的可能性被认为是燃料元件商业化后处理的替代方法。最终处置的目的是将放射性物质与生物圈隔离,并与没有时间限制的人类意外进入的可能性隔离。安全概念旨在确保存储库的完整性,而在最终关闭存储库后无需人工维护或监控。最终处置被认为是不可逆转的处置。在“替代废物管理技术”研究与开发计划的框架内,正在研究将乏燃料元素放入盐丘中的情况。已为最终处置罐和最终用于乏燃料元件的直接处置的安置技术汇编了几种概念。在每种情况下,均选择了一个最能满足安全工程标准1的技术可行性,原材料可得性以及经济效率和核材料保障措施1的概念作为参考。在确定参考概念的基础上,还确定了每个组件的备份解决方案。 KFA-TUG将在参考概念的基础上制定核材料保障概念。替代废物管理的这一保障概念包括保护产品,使其从到达地质处置库起就进行最终处置。第一章已选择并汇编了对实施国际保障措施重要的各个方面。 2取决于此概念所需的大量信息以及已知的详细技术问题。[...]

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