玻璃化
硼硅酸盐玻璃
放射性废物
高水平废物
乏核燃料
废物管理
材料科学
环境科学
萨凡纳河基地
陶瓷
相(物质)
核工程
放射化学
冶金
化学
工程类
有机化学
医学
男科
作者
Akira Sakai,S. Weisenburger,Ian L. Pegg,Shuichi Ishida
标识
DOI:10.1080/00295450.2023.2266612
摘要
The Rokkasho Reprocessing Plant, located in northern Japan, includes facilities for reprocessing spent nuclear fuels and immobilizing high-level waste (HLW) into a stable-glass waste form based on borosilicate. The vitrification process consists of two large liquid-fed, joule-heated, ceramic-lined melters (LFCMs). During the active test campaigns at the Rokkasho Vitrification Facility, unstable melting performance and difficulty in glass operation were observed in the LFCM operation. The operating protocols that had been developed in the earlier full-scale mock-up testing with inactive waste simulants were found to be inadequate to manage a stable LFCM operation.
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