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Purification of U from U-10Mo scrap generated during the fabrication of high performance research reactor fuel.

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Title: Purification of U from U-10Mo scrap generated during the fabrication of high performance research reactor fuel.
Authors: Rudisill, Tracy S.1 (AUTHOR) tracy.rudisill@srnl.doe.gov, Pereira, Candido2 (AUTHOR)
Source: Separation Science & Technology. 2026, Vol. 61 Issue 3-5, p501-513. 13p.
Subjects: Solvent extraction, Research reactors, Nuclear fuels, Uranium mining, Uranium enrichment
Geographic Terms: United States
Abstract: A low enriched U-Mo alloy fuel is under development to replace highly enriched U fuels currently used in United States high performance research reactors. The alloy casting and fuel fabrication processes will generate scrap streams containing low enriched U (LEU) which must be recovered. Solvent extraction processes were designed using the Argonne Model for Universal Solvent Extraction (AMUSE) to purify solutions containing 20 and 50 g/L U. The feed for the solvent extraction processes was prepared from solutions generated from the dissolution of U-10Mo-Zr foils and U-10Mo-Zr-Al mini-plates. The U purification processes were demonstrated using two, 16-stage banks of miniature mixer-settlers. The solvent extraction experiments demonstrated that all design objectives for the U purification processes could be met. The U recovery in the product stream for each flowsheet was ≥99.9%. The flowsheet demonstrations also showed that the purity of the U Product will meet the requirements of the ASTM International C1462-21 specification for LEU metal enriched to less than 20% 235U. The AMUSE modeling for both flowsheet demonstrations was validated by comparing predicted and measured concentrations of U, Mo, and Zr in the exit streams and stage samples at steady-state conditions in the mixer-settlers. [ABSTRACT FROM AUTHOR]
Copyright of Separation Science & Technology is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
Database: Engineering Source
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DbLabel: Engineering Source
An: 191349112
AccessLevel: 6
PubType: Academic Journal
PubTypeId: academicJournal
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  Data: Purification of U from U-10Mo scrap generated during the fabrication of high performance research reactor fuel.
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  Data: <searchLink fieldCode="AR" term="%22Rudisill%2C+Tracy+S%2E%22">Rudisill, Tracy S.</searchLink><relatesTo>1</relatesTo> (AUTHOR)<i> tracy.rudisill@srnl.doe.gov</i><br /><searchLink fieldCode="AR" term="%22Pereira%2C+Candido%22">Pereira, Candido</searchLink><relatesTo>2</relatesTo> (AUTHOR)
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  Data: <searchLink fieldCode="JN" term="%22Separation+Science+%26+Technology%22">Separation Science & Technology</searchLink>. 2026, Vol. 61 Issue 3-5, p501-513. 13p.
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  Data: <searchLink fieldCode="DE" term="%22Solvent+extraction%22">Solvent extraction</searchLink><br /><searchLink fieldCode="DE" term="%22Research+reactors%22">Research reactors</searchLink><br /><searchLink fieldCode="DE" term="%22Nuclear+fuels%22">Nuclear fuels</searchLink><br /><searchLink fieldCode="DE" term="%22Uranium+mining%22">Uranium mining</searchLink><br /><searchLink fieldCode="DE" term="%22Uranium+enrichment%22">Uranium enrichment</searchLink>
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  Data: <searchLink fieldCode="DE" term="%22United+States%22">United States</searchLink>
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  Label: Abstract
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  Data: A low enriched U-Mo alloy fuel is under development to replace highly enriched U fuels currently used in United States high performance research reactors. The alloy casting and fuel fabrication processes will generate scrap streams containing low enriched U (LEU) which must be recovered. Solvent extraction processes were designed using the Argonne Model for Universal Solvent Extraction (AMUSE) to purify solutions containing 20 and 50 g/L U. The feed for the solvent extraction processes was prepared from solutions generated from the dissolution of U-10Mo-Zr foils and U-10Mo-Zr-Al mini-plates. The U purification processes were demonstrated using two, 16-stage banks of miniature mixer-settlers. The solvent extraction experiments demonstrated that all design objectives for the U purification processes could be met. The U recovery in the product stream for each flowsheet was ≥99.9%. The flowsheet demonstrations also showed that the purity of the U Product will meet the requirements of the ASTM International C1462-21 specification for LEU metal enriched to less than 20% 235U. The AMUSE modeling for both flowsheet demonstrations was validated by comparing predicted and measured concentrations of U, Mo, and Zr in the exit streams and stage samples at steady-state conditions in the mixer-settlers. [ABSTRACT FROM AUTHOR]
– Name: AbstractSuppliedCopyright
  Label:
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  Data: <i>Copyright of Separation Science & Technology is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.)
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        Value: 10.1080/01496395.2024.2428357
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      – Code: eng
        Text: English
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        PageCount: 13
        StartPage: 501
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      – SubjectFull: Solvent extraction
        Type: general
      – SubjectFull: Research reactors
        Type: general
      – SubjectFull: Nuclear fuels
        Type: general
      – SubjectFull: Uranium mining
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      – SubjectFull: Uranium enrichment
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      – SubjectFull: United States
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      – TitleFull: Purification of U from U-10Mo scrap generated during the fabrication of high performance research reactor fuel.
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            NameFull: Pereira, Candido
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              M: 03
              Text: 2026
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