Technetium and Iodine Separations in the UREX Process.

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The Accelerator Transmutation of Waste (ATW) program is being developed to determine the feasibility of separatin and transmutating the transactinides (Pu-Cm) and long-lived fission product (99Tc and 'I) from spent light water reactor (LWR) fuel. This approach would help with the disposal of spent commercial fuel. In addition, since the residual waste after ATW treatment will have much lower levels of long-lived species, this process may improve the performance and acceptability of long-term geologic disposal of nuclear waste. A roadmap for the Accelerator Transmutation of Waste (ATW) was submitted to Congress in 1999.' This document gave an overall view of ... continued below

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30 p.

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Schroeder, N. C. (Norman C.); Attrep, Moses & Marrero, T. (Thomas) January 1, 2001.

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Description

The Accelerator Transmutation of Waste (ATW) program is being developed to determine the feasibility of separatin and transmutating the transactinides (Pu-Cm) and long-lived fission product (99Tc and 'I) from spent light water reactor (LWR) fuel. This approach would help with the disposal of spent commercial fuel. In addition, since the residual waste after ATW treatment will have much lower levels of long-lived species, this process may improve the performance and acceptability of long-term geologic disposal of nuclear waste. A roadmap for the Accelerator Transmutation of Waste (ATW) was submitted to Congress in 1999.' This document gave an overall view of the ATW concept and program. A subsequent document prepared by the Technical Working Group for ATW Separations Technologies and Waste Forms issued a second roadmap that dealt more specifically with the radionuclide separations and waste disposal needs for the ATW program.' This latter document discusses the UREX (Uranium Extraction) process. The latest iteration of the UREX flowsheet is shown in Figure le3T his flowsheet anticipates the co-extraction of technetium with uranium from dissolved LWR fuel by tributylphosphate (TBP) and their subsequent sequential bwk-extraction from the TBP stream.

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30 p.

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  • Submitted to: Accelerator Transmutation of Waste Program Office.

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  • Report No.: LA-UR-01-6607
  • Grant Number: none
  • Office of Scientific & Technical Information Report Number: 975891
  • Archival Resource Key: ark:/67531/metadc927724

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • January 1, 2001

Added to The UNT Digital Library

  • Nov. 13, 2016, 7:26 p.m.

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  • Dec. 12, 2016, 1:38 p.m.

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Schroeder, N. C. (Norman C.); Attrep, Moses & Marrero, T. (Thomas). Technetium and Iodine Separations in the UREX Process., article, January 1, 2001; United States. (digital.library.unt.edu/ark:/67531/metadc927724/: accessed June 24, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.