{"title":"评价六氰高铁酸铝对PGM的利用和对模拟高水平后萃物中Mo的去除,以减少储存库面积","authors":"Masahiko Nakase , Ria Mishima , Takumi Abe , Tomohiro Okamura , Hidekazu Asano","doi":"10.1016/j.anucene.2025.111569","DOIUrl":null,"url":null,"abstract":"<div><div>Higher burnup LWR and MOX spent fuels contain increased levels of Platinum Group Metals (PGMs; Pd, Ru, Rh) and Mo, necessitating their control to ensure stable glass melter operations and prevent yellow phase formation, thereby maintaining vitrified glass quality. Separating PGMs and Mo during reprocessing can significantly reduce the repository space required for vitrified high-level wastes (HLWs). This study explores the use of Aluminum Hexacyanoferrate (AlHCF) for simultaneous separation of PGMs and Mo, which involves the elution of structural Al during sorption. A fundamental methodology was developed for analyzing the back-end processes of the nuclear fuel cycle (NFC), focusing on the quantitative impact of AlHCF. By integrating adsorption experiments of simulated high-level liquid waste (sHLLW) with mass balance calculations and thermal conductive calculation via NMB 4.0, the study identified practical AlHCF utilization conditions (11 to 40 wt% waste loading and 100 to 200 kg/tHM of AlHCF). It also established the relationship between AlHCF amount, waste loading, and reductions in both vitrified waste and repository size, highlighting optimal conditions for minimizing repository footprint.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111569"},"PeriodicalIF":2.3000,"publicationDate":"2025-07-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Evaluation of Aluminum Hexacyanoferrate utilization for PGM and Mo removal from simulated high-level-raffinates in reprocessing for repository area minimization\",\"authors\":\"Masahiko Nakase , Ria Mishima , Takumi Abe , Tomohiro Okamura , Hidekazu Asano\",\"doi\":\"10.1016/j.anucene.2025.111569\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Higher burnup LWR and MOX spent fuels contain increased levels of Platinum Group Metals (PGMs; Pd, Ru, Rh) and Mo, necessitating their control to ensure stable glass melter operations and prevent yellow phase formation, thereby maintaining vitrified glass quality. Separating PGMs and Mo during reprocessing can significantly reduce the repository space required for vitrified high-level wastes (HLWs). This study explores the use of Aluminum Hexacyanoferrate (AlHCF) for simultaneous separation of PGMs and Mo, which involves the elution of structural Al during sorption. A fundamental methodology was developed for analyzing the back-end processes of the nuclear fuel cycle (NFC), focusing on the quantitative impact of AlHCF. By integrating adsorption experiments of simulated high-level liquid waste (sHLLW) with mass balance calculations and thermal conductive calculation via NMB 4.0, the study identified practical AlHCF utilization conditions (11 to 40 wt% waste loading and 100 to 200 kg/tHM of AlHCF). It also established the relationship between AlHCF amount, waste loading, and reductions in both vitrified waste and repository size, highlighting optimal conditions for minimizing repository footprint.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":\"224 \",\"pages\":\"Article 111569\"},\"PeriodicalIF\":2.3000,\"publicationDate\":\"2025-07-04\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Annals of Nuclear Energy\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S030645492500386X\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S030645492500386X","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Evaluation of Aluminum Hexacyanoferrate utilization for PGM and Mo removal from simulated high-level-raffinates in reprocessing for repository area minimization
Higher burnup LWR and MOX spent fuels contain increased levels of Platinum Group Metals (PGMs; Pd, Ru, Rh) and Mo, necessitating their control to ensure stable glass melter operations and prevent yellow phase formation, thereby maintaining vitrified glass quality. Separating PGMs and Mo during reprocessing can significantly reduce the repository space required for vitrified high-level wastes (HLWs). This study explores the use of Aluminum Hexacyanoferrate (AlHCF) for simultaneous separation of PGMs and Mo, which involves the elution of structural Al during sorption. A fundamental methodology was developed for analyzing the back-end processes of the nuclear fuel cycle (NFC), focusing on the quantitative impact of AlHCF. By integrating adsorption experiments of simulated high-level liquid waste (sHLLW) with mass balance calculations and thermal conductive calculation via NMB 4.0, the study identified practical AlHCF utilization conditions (11 to 40 wt% waste loading and 100 to 200 kg/tHM of AlHCF). It also established the relationship between AlHCF amount, waste loading, and reductions in both vitrified waste and repository size, highlighting optimal conditions for minimizing repository footprint.
期刊介绍:
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.