Immobilization of 137Cs in NaY type zeolite matrices using various heat treatment methods

IF 3.4 3区化学 Q2 CHEMISTRY, INORGANIC & NUCLEAR

Solid State Sciences Pub Date : 2024-07-05 DOI:10.1016/j.solidstatesciences.2024.107619

O.O Shichalin , E.K. Papynov , A.A. Belov , N.P. Ivanov , I.Yu Buravlev , A.O. Lembikov , M.I. Dvornik , P.G. Chigrin , N.M. Vlasova , Yu.A. Mirovoy , N.D. Kulagin , E.S. Mirovaya , A.V. Syuy , T.A. Borisenko , A.V. Ukhina , V.O. Kaptakov , A.P. Zavjalov , Yun Shi , A.I. Ivanets

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Abstract

The accumulation of liquid radioactive waste presents a significant global challenge, necessitating effective strategies for safe management. This study investigates the immobilization of ¹³⁷Cs radionuclides, a prominent component of liquid radioactive waste, in ceramic matrices based on ¹³⁷Cs-saturated NaY Faujasite zeolite. Various thermal methods were employed, including cold pressing and sintering, cold pressing and sintering with microwave assistance, hot pressing, and spark plasma sintering, to enhance immobilization capabilities. Zeolite powder was saturated with ¹³⁷Cs radionuclides using an adsorption technique with low-activity model liquid radioactive waste. In-situ XRD and dilatometry methods were used to study the thermal behavior during NaY Faujasite annealing. The influence of calcination temperature on lattice parameters and crystallite size was assessed. Immobilization effectiveness was evaluated through relative density, Vickers microhardness, compressive strength, and metal ion leaching kinetics. Mechanistic evaluation was performed using XRD and SEM-EDX studies. Results showed that spark plasma sintering exhibited the highest efficiency for immobilizing ¹³⁷Cs radionuclides in NaY Faujasite matrices. This research contributes to liquid radioactive waste management by providing insights into the thermal behavior and enhanced immobilization capabilities of ceramic matrices.

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使用各种热处理方法在 NaY 型沸石基质中固定 137Cs

液态放射性废物的积累是一项重大的全球性挑战，需要采取有效的安全管理策略。本研究以 137Cs 饱和 NaY Faujasite 沸石为基础，调查了 137Cs 放射性核素（液态放射性废物的主要成分）在陶瓷基质中的固定情况。为了提高固定化能力，采用了多种热方法，包括冷压烧结、微波辅助冷压烧结、热压烧结和火花等离子烧结。利用低活度模型液体放射性废物吸附技术，使沸石粉末饱和 137Cs 放射性核素。采用原位 XRD 和扩张仪方法研究了 NaY Faujasite 退火过程中的热行为。评估了煅烧温度对晶格参数和晶体尺寸的影响。通过相对密度、维氏显微硬度、抗压强度和金属离子浸出动力学评估了固定化效果。利用 XRD 和 SEM-EDX 研究对机理进行了评估。结果表明，火花等离子烧结在固定 NaY Faujasite 基质中的 137Cs 放射性核素方面效率最高。这项研究有助于了解陶瓷基质的热行为和增强固定能力，从而为液态放射性废物管理做出贡献。

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来源期刊

Solid State Sciences 化学-无机化学与核化学

CiteScore

6.60

自引率

2.90%

发文量

214

审稿时长

27 days

期刊介绍： Solid State Sciences is the journal for researchers from the broad solid state chemistry and physics community. It publishes key articles on all aspects of solid state synthesis, structure-property relationships, theory and functionalities, in relation with experiments. Key topics for stand-alone papers and special issues: -Novel ways of synthesis, inorganic functional materials, including porous and glassy materials, hybrid organic-inorganic compounds and nanomaterials -Physical properties, emphasizing but not limited to the electrical, magnetical and optical features -Materials related to information technology and energy and environmental sciences. The journal publishes feature articles from experts in the field upon invitation. Solid State Sciences - your gateway to energy-related materials.