Immobilisation of Higher Activity Wastes from Nuclear Reactor Production of 99Mo
A variety of intermediate- and low-level liquid and solid wastes are produced from reactor production of 99Mo 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...
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| Main Authors: | , , , , , , |
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| Format: | Article |
| Language: | English |
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Wiley
2013-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2013/926026 |
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| author | Martin W. A. Stewart Eric R. Vance Sam A. Moricca Daniel R. Brew Catherine Cheung Tina Eddowes Walter Bermudez |
| author_facet | Martin W. A. Stewart Eric R. Vance Sam A. Moricca Daniel R. Brew Catherine Cheung Tina Eddowes Walter Bermudez |
| author_sort | Martin W. A. Stewart |
| collection | DOAJ |
| description | A variety of intermediate- and low-level liquid and solid wastes are produced from reactor production of 99Mo 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 99Mo. 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. |
| format | Article |
| id | doaj-art-77262411e65548d1af0e19475a88d97f |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2013-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-77262411e65548d1af0e19475a88d97f2025-02-03T06:06:19ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832013-01-01201310.1155/2013/926026926026Immobilisation of Higher Activity Wastes from Nuclear Reactor Production of 99MoMartin W. A. Stewart0Eric R. Vance1Sam A. Moricca2Daniel R. Brew3Catherine Cheung4Tina Eddowes5Walter Bermudez6Australian Nuclear Science and Technology Organisation (ANSTO), New Illawarra Road, Lucas Heights, NSW 2234, AustraliaAustralian Nuclear Science and Technology Organisation (ANSTO), New Illawarra Road, Lucas Heights, NSW 2234, AustraliaAustralian Nuclear Science and Technology Organisation (ANSTO), New Illawarra Road, Lucas Heights, NSW 2234, AustraliaAustralian Nuclear Science and Technology Organisation (ANSTO), New Illawarra Road, Lucas Heights, NSW 2234, AustraliaAustralian Nuclear Science and Technology Organisation (ANSTO), New Illawarra Road, Lucas Heights, NSW 2234, AustraliaAustralian Nuclear Science and Technology Organisation (ANSTO), New Illawarra Road, Lucas Heights, NSW 2234, AustraliaAustralian Nuclear Science and Technology Organisation (ANSTO), New Illawarra Road, Lucas Heights, NSW 2234, AustraliaA variety of intermediate- and low-level liquid and solid wastes are produced from reactor production of 99Mo 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 99Mo. 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.http://dx.doi.org/10.1155/2013/926026 |
| spellingShingle | Martin W. A. Stewart Eric R. Vance Sam A. Moricca Daniel R. Brew Catherine Cheung Tina Eddowes Walter Bermudez Immobilisation of Higher Activity Wastes from Nuclear Reactor Production of 99Mo Science and Technology of Nuclear Installations |
| title | Immobilisation of Higher Activity Wastes from Nuclear Reactor Production of 99Mo |
| title_full | Immobilisation of Higher Activity Wastes from Nuclear Reactor Production of 99Mo |
| title_fullStr | Immobilisation of Higher Activity Wastes from Nuclear Reactor Production of 99Mo |
| title_full_unstemmed | Immobilisation of Higher Activity Wastes from Nuclear Reactor Production of 99Mo |
| title_short | Immobilisation of Higher Activity Wastes from Nuclear Reactor Production of 99Mo |
| title_sort | immobilisation of higher activity wastes from nuclear reactor production of 99mo |
| url | http://dx.doi.org/10.1155/2013/926026 |
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