Investigations on measurement and methodology for dielectric constant of solvents used for actinide separations in nuclear fuel cycle

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-02-01 Epub Date: 2024-12-10 DOI:10.1016/j.nucengdes.2024.113734
Ajay Kumar Keshari , J. Prabhakar Rao , C.V.S. Brahmananda Rao
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Abstract

PUREX (Plutonium uranium reduction extraction) is a versatile reprocessing method being employed in nuclear fuel cycle to separate U/Pu from the spent fuel present in 4 M nitric acid medium. The process is carried out by using 1.1 M tributyl phosphate (TBP)/n-DD (dodecane) as the extractant. High aqueous solubility and radiological and chemical degradation followed by retention of actinides are major disadvantages. However, to overcome certain demerits encountered by TBP and other alkyl phosphate-based extractants, organic phosphonate-based extractants have been developed and used to extract actinide.
Various organophosphorous based solvents are synthesized to develop better extractants for separation and recovery of actinides by solvent extraction in nuclear reactor/allied facilities. The polarity of the organic phase in the solvent extraction is a key parameter, which determines the amount of metal that can be loaded in the organic phase. The dielectric constant is an admissible ability to dissolve common ionic compounds. Typically, the dielectric constant of a solvent is evaluated for polarity. Higher dielectric constant is a measure of higher polarity, and greater is the capability of the solvent to hold the steady charges. The instrumentation setup is devised and developed for the measurement of the dielectric constant of solvents in a given medium The challenge in the setup is developing a dielectric sensor and instrumentation, that is compatible with sophisticated solvents possessing wide dynamic response with high accuracy, stability and precision. The investigations of the sensor, measurement methodology and estimation of the dielectric constant with various known and unknown solvents for the separation and recovery of actinides in the nuclear fuel cycle and nuclear waste treatment of the fast breeder test reactor were carried out and studied in detail. The dielectric constant of various standard solvents lying in the range 1–40 was measured and validated from literature values with an accuracy of ±1 %. Subsequently, the measurement of dielectric constant was carried out over different solvents such as Di-iso-amyl-iso-amyl phosphonate (DiAiAP), Di-iso-amyl-butyl phosphonate (DiABP), Di-sec-amyl-hydrogen phosphonate (DsAHP) and Di-sec-butyl-hydrogen phosphonate (DsBHP) synthesized in our laboratory.
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核燃料循环中分离锕系元素所用溶剂介电常数的测量和方法学研究
PUREX(钚铀还原萃取)是一种用于核燃料循环的多功能后处理方法,用于从存在于4 M硝酸介质中的乏燃料中分离U/Pu。该工艺以1.1 M磷酸三丁酯(TBP)/n-DD(十二烷)为萃取剂进行。高水溶性和放射性和化学降解后保留锕系元素是主要的缺点。然而,为了克服TBP和其他烷基磷酸盐基萃取剂所遇到的某些缺点,人们开发了有机磷酸盐基萃取剂,并将其用于提取锕系元素。合成了多种有机磷基溶剂,以开发出更好的萃取剂,用于核反应堆或相关设施中锕系元素的溶剂萃取分离和回收。溶剂萃取中有机相的极性是一个关键参数,它决定了有机相中金属的负载量。介电常数是溶解普通离子化合物的可接受能力。通常,溶剂的介电常数是用极性来评价的。较高的介电常数表示较高的极性,溶剂保持稳定电荷的能力也越大。该仪器装置是为测量给定介质中溶剂的介电常数而设计和开发的,该装置的挑战是开发一种与复杂溶剂兼容的介电传感器和仪器,具有广泛的动态响应,具有高精度、稳定性和精密度。对快中子增殖试验堆燃料循环和核废料处理中锕系元素分离回收用各种已知和未知溶剂的传感器、测量方法和介电常数估算进行了详细的研究。测量了1 - 40范围内各种标准溶剂的介电常数,并根据文献值进行了验证,准确度为±1%。随后,在实验室合成的不同溶剂如二异戊基膦酸酯(DiAiAP)、二异戊基膦酸酯(DiABP)、二叔戊基膦酸酯(DsAHP)和二叔丁基膦酸酯(dshbhp)上进行介电常数的测量。
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
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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