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Search for Solving the Problem of Conditioning the Reactor Graphite
Radiochemistry Pub Date : 2020-07-08 , DOI: 10.1134/s1066362220030017
Yu. A. Pokhitonov

Abstract

Spent reactor graphite constitutes a significant part of the accumulated solid radioactive wastes, and a search for its isolation from the biosphere is a topical task. Radioactive nuclides are listed in the paper, the activity of which determines the degree of contamination of the graphite stack and other construction elements of decommissioned uranium-graphite reactors. The suggested technical solutions must be based on a differentiated approach to various kinds of a graphite waste, which differ in the specific activity and spectrum of radionuclides. A preliminary fractionation (assortment) will make it possible to many times diminish the amount of waste delivered to the point of deep burial. A search for approaches to graphite processing must be subordinate to the problem of finding the less expensive technologies. Any procedure aimed to process graphite to remove 14C and 36Cl into a separate product will only make larger the total waste volume and require an additional expenditure. The development of even the most effective methods cannot provide the economic effect that can be obtained if the regulations on the content of impurities in graphite are reconsidered and a safe burial of the reactor graphite in near-surface storages is substantiated.


中文翻译:

寻找解决反应堆石墨问题的方法

摘要

用过的反应堆石墨构成了累积的固体放射性废物的重要组成部分,寻找将其与生物圈隔离的工作是一项艰巨的任务。论文中列出了放射性核素,放射性核素的活性决定了退役铀-石墨反应堆中石墨堆和其他结构元件的污染程度。建议的技术解决方案必须基于对各种石墨废料的区别对待方法,这些废料的比活度和放射性核素的光谱不同。初步的分馏(分类)将使许多次减少到深埋点的废物数量成为可能。寻找石墨加工方法必须服从于寻找较便宜的技术的问题。将14 C和36 Cl分离成一个单独的产品只会增加总废物量,并且需要额外的支出。如果重新考虑有关石墨中杂质含量的规定,并证实在近地表储存器中安全掩埋反应堆石墨,那么即使是最有效的方法的开发也无法提供经济效果。
更新日期:2020-07-08
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