用废吸附剂固定化分离镅和锔至磷酸镁钾化合物

IF 0.3 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY
S. A. Fimina, N. D. Chalysheva, K. Yu. Belova, B. V. Savel’ev, S. E. Vinokurov
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引用次数: 0

摘要

作为Proryv项目的一部分,乏氮燃料后处理的最后阶段涉及使用置换络合色谱法在阳离子交换吸附剂上分离镅和curium。为了环境的放射生态安全,废放射性吸附剂应转化为稳定的化合物。目的测试磷酸镁钾(MPP)基质对乏氮燃料后处理过程中形成的乏放射性吸附剂的固定化作用,并确定所得MPP化合物的质量指标。材料和方法用X射线衍射法测定所得样品的相组成。根据标准试验测定了样品的耐水性、机械抗压强度、抗热冻融循环能力以及基质形成元素和241、243Am和244Cm同位素的浸出性。所得的MPP化合物样品含有高达20% wt %的废吸附模拟剂和10% wt %的硅灰石;它们的主要晶相与天然矿物K鸟粪石类似。MPP复合材料的抗压强度为~6 MPa,包括在水中浸泡90天后完成的冻融和耐水试验。该化合物具有很强的抗基质形成元素和同位素浸出能力:241,243am和244Cm的浸出率分别约为5.8∙10−7和2.5∙10−7 g/(cm2∙day)。结论应用MPP复合材料固定化乏氮燃料后处理过程中形成的放射性吸附剂具有广阔的应用前景。所得样品的质量指标符合放射性废物固化的要求。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Immobilization of spent sorbent for separation of americium and curium into magnesium potassium phosphate compound

Background

As part of the Proryv project, the final stage of reprocessing spent nitride fuel involves the separation of americium and curium on a cation-exchange sorbent using displacement complexation chromatography. For radioecological safety of the environment, spent radioactive sorbent should be converted into a stable compound.

Aim

To test magnesium potassium phosphate (MPP) matrix for immobilization of spent radioactive sorbent formed during the reprocessing of spent nitride fuel, as well as to determine the quality indicators of the resulting MPP compound.

Materials and methods

The phase composition of obtained samples was determined by X‑ray diffractometry. Water resistance, mechanical compressive strength, resistance to thermal freeze-thaw cycles, as well as leaching of matrix-forming elements and 241, 243Am and 244Cm isotopes was determined in accordance with standard tests.

Results and discussion

The obtained samples of MPP compound contain up to 20 wt % of the spent sorbent simulant and 10 wt % of wollastonite; their main crystalline phase represents an analogue of the K‑struvite natural mineral. The compressive strength of MPP compound is ~6 MPa, including upon the completion of freeze-thaw and water resistance tests after 90 days of immersion in water. The compound is demonstrated highly resistant to leaching of matrix-forming elements and isotopes: the leaching rate of 241, 243Am and 244Cm is approximately 5.8∙10−7 and 2.5∙10−7 g/(cm2∙day), respectively.

Conclusion

The prospects of using MPP compound for immobilization of spent radioactive sorbent formed during reprocessing of spent nitride fuel are shown. Quality indicators of obtained samples 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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