用于固化废磷酸三丁酯-十二烷模拟剂的磷酸镁钾基质

IF 0.3 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY Atomic Energy Pub Date : 2025-01-17 DOI:10.1007/s10512-024-01163-y
S. A. Fimina, K. Yu. Belova, N. D. Chalysheva, S. E. Vinokurov
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引用次数: 0

摘要

在湿法冶金燃料后处理过程中,稀释剂中的废萃取剂会累积。萃取剂中的稀释剂归类为液态放射性废物,必须将其转化为环境安全状态。本文介绍了用磷酸镁钾基质固化废磷酸三丁酯-十二烷模拟剂的试验结果。我们根据GOST R 52126-2003测试了固化样品的抗压强度、浸泡90天后的水稳定性、循环冻融(从- 40到40 °C 30个循环)的耐受性和耐水性。因此,磷酸镁钾化合物可包括高达20% wt%的预饱和的与磷酸三丁酯-十二烷混合物的航煤。这相当于稀释剂中萃取剂的17.6 wt%。此外,所研究的化合物的质量指标满足固化放射性废物的要求。
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Magnesium potassium phosphate matrix for solidification of a spent tributyl phosphate—dodecane simulant

Spent extractant in a diluent accumulates of hydrometallurgical fuel reprocessing. Extractant in a diluent classified as liquid radioactive waste, which must be converted into an environmentally safe state. The article presents the results of testing a magnesium potassium phosphate matrix for solidifying a spent tributyl phosphate—dodecane simulant. We examined solidified samples for compressive strength, water stability after 90 days of immersion, resistance to cycling freezing and thawing (30 cycles from −40 to 40 °C), and water resistance in accordance with GOST R 52126–2003. Thus, a magnesium potassium phosphate compound can include up to 20 wt% of aerosil pre-saturated with a tributyl phosphate—dodecane mixture. This corresponds to 17.6 wt% of the extractant in the diluent. Moreover, quality indicators of the studied compound meet the requirements for solidified radioactive waste.

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来源期刊
Atomic Energy
Atomic Energy 工程技术-核科学技术
CiteScore
1.00
自引率
20.00%
发文量
100
审稿时长
4-8 weeks
期刊介绍: Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.
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