Immobilisation of Higher Activity Wastes from Nuclear Reactor Production of 99Mo. (30th December 2013)

• Record Type: Journal Article
• Authors: Stewart, Martin W. A.; Vance, Eric R.; Moricca, Sam A.; Brew, Daniel R.; Cheung, Catherine; Eddowes, Tina; Bermudez, Walter
• Other Names: Ahmad Mushtaq Academic Editor.
• Is Part Of: Science and technology of nuclear installations. Volume 2013(2013)
• Publication Date: 2013-12-30
• Subjects: Nuclear engineering -- Periodicals; Nuclear facilities -- Periodicals; Nuclear engineering; Nuclear facilities; Electronic journals; Periodicals; 621.48
• DOI: 10.1155/2013/926026
• Languages: English
• ISSNs: 1687-6075

Abstract

Abstract : A variety of intermediate- and low-level liquid and solid wastes are produced from reactor production of 99 Mo using UAl alloy or UO2 targets and in principle can be collectively or individually converted into waste forms. At ANSTO, we have legacy acidic uranyl-nitrate-rich intermediate level waste (ILW) from the latter, and an alkaline liquid ILW, a U-rich filter cake, plus a shorter lived liquid stream that rapidly decays to low-level waste (LLW) standards, from the former. The options considered consist of cementitious products, glasses, glass-ceramics, or ceramics produced by vitrification or hot isostatic pressing for intermediate-level wastes. This paper discusses the progress in waste form development and processing to treat ANSTO's ILW streams arising from 99 Mo. The various waste forms and the reason for the process option chosen will be reviewed. We also address the concerns over adapting our chosen process for use in a hot-cell environment.