{"title":"Immobilization of chloride radioactive waste using a phosphate glass composite material","authors":"A. V. Frolova, S. A. Fimina, S. E. Vinokurov","doi":"10.1007/s10512-024-01062-2","DOIUrl":null,"url":null,"abstract":"<p>The article confirms the possibility of using a two-component iron-phosphate glass composite material synthesized at 700 °C to immobilize a simulator of a highly-active spent chloride electrolyte, such as those obtained in the pyrochemical processing of the spent mixed uranium-plutonium fuel of a BREST-OD-300 reactor. The structure and phase composition of the material were studied using scanning electron microscopy with energy-dispersion X‑ray spectroscopy, X‑ray fluorescence analysis, and X-ray powder diffractometry. The waste components are shown to form stable pyrophosphate phases. The material leachability of waste components is defined according to the PCT standard. The glass composite material is highly water resistant. Thus, the prospects for the practical application of the studied material for the reliable immobilization of spent electrolyte materials are demonstrated.</p>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":null,"pages":null},"PeriodicalIF":0.4000,"publicationDate":"2024-04-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Atomic Energy","FirstCategoryId":"5","ListUrlMain":"https://doi.org/10.1007/s10512-024-01062-2","RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
The article confirms the possibility of using a two-component iron-phosphate glass composite material synthesized at 700 °C to immobilize a simulator of a highly-active spent chloride electrolyte, such as those obtained in the pyrochemical processing of the spent mixed uranium-plutonium fuel of a BREST-OD-300 reactor. The structure and phase composition of the material were studied using scanning electron microscopy with energy-dispersion X‑ray spectroscopy, X‑ray fluorescence analysis, and X-ray powder diffractometry. The waste components are shown to form stable pyrophosphate phases. The material leachability of waste components is defined according to the PCT standard. The glass composite material is highly water resistant. Thus, the prospects for the practical application of the studied material for the reliable immobilization of spent electrolyte materials are demonstrated.
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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