Liquid metal reactor deactivation as applied to the experimental breeder reactor - II.

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The Experimental Breeder Reactor-II (EBR-II) at Argonne National Laboratory-West (ANL-W) was shutdown in September, 1994. This sodium cooled reactor had been in service since 1964, and by the US Department of Energy (DOE) mandate, was to be placed in an industrially and radiologically safe condition for ultimate decommissioning. The deactivation of a liquid metal reactor presents unique concerns. The first major task associated with the project was the removal of all fueled assemblies. In addition, sodium must be drained from systems and processed for ultimate disposal. Residual quantities of sodium remaining in systems must be deactivated or inerted to preclude ... continued below

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16 p.

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Earle, O. K.; Michelbacher, J. A.; Pfannenstiel, D. F. & Wells, P. B. May 28, 1999.

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Description

The Experimental Breeder Reactor-II (EBR-II) at Argonne National Laboratory-West (ANL-W) was shutdown in September, 1994. This sodium cooled reactor had been in service since 1964, and by the US Department of Energy (DOE) mandate, was to be placed in an industrially and radiologically safe condition for ultimate decommissioning. The deactivation of a liquid metal reactor presents unique concerns. The first major task associated with the project was the removal of all fueled assemblies. In addition, sodium must be drained from systems and processed for ultimate disposal. Residual quantities of sodium remaining in systems must be deactivated or inerted to preclude future hazards associated with pyrophoricity and generation of potentially explosive hydrogen gas. A Sodium Process Facility (SPF) was designed and constructed to react the elemental sodium from the EBR-II primary and secondary systems to sodium hydroxide for disposal. This facility has a design capacity to allow the reaction of the complete inventory of sodium at ANL-W in less than two years. Additional quantities of sodium from the Fermi-1 reactor are also being treated at the SPF.

Physical Description

16 p.

Notes

INIS; OSTI as DE00011741

Medium: P; Size: 16 pages

Source

  • American Nuclear Society 2nd Topical Meeting on Decommissioning, Decontamination and Reutilization of Commercial and Government Facilities, Knoxville, TN (US), 09/12/1999--09/16/1999

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  • Report No.: ANL/ED/CP-98713
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 11741
  • Archival Resource Key: ark:/67531/metadc619951

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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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  • May 28, 1999

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

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  • April 7, 2017, 3:18 p.m.

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Earle, O. K.; Michelbacher, J. A.; Pfannenstiel, D. F. & Wells, P. B. Liquid metal reactor deactivation as applied to the experimental breeder reactor - II., article, May 28, 1999; Illinois. (digital.library.unt.edu/ark:/67531/metadc619951/: accessed November 20, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.