Methodological approaches to the survey of storage facilities for the radioactive waste from uranium-graphite reactors

IF 2.1 Q3 ENGINEERING, ENVIRONMENTAL
A. Pavliuk, S. Kotlyarevsky, V. S. Zagumennov, R. Kan, V. A. Kuzov, A. V. Mevius
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引用次数: 0

Abstract

The article presents methods and a general survey procedure for storage facilities with radioactive waste generated during the operation of uranium-graphite reactors. It presents the experience from the application of different survey methods and relevant findings. The paper describes the key areas for further improvement of the survey methods, including the results from the mock-up tests based on various methods applied for arranging penetrations in the radioactive waste volume providing access to the bottom waste layers. The approaches presented in the article can be adapted to explore other storage facility types arranged during nuclear decommissioning.
铀-石墨反应堆放射性废料贮存设施调查的方法学方法
本文介绍了铀-石墨堆运行过程中产生的放射性废物贮存设施的测量方法和一般程序。它介绍了不同调查方法的应用经验和相关发现。本文描述了进一步改进调查方法的关键领域,包括基于在放射性废物容积中布置穿透点以提供通往底部废物层的各种方法的模拟试验结果。本文提出的方法可适用于探索核退役期间安排的其他储存设施类型。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
CiteScore
5.40
自引率
7.40%
发文量
80
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