Repository performance assessment of waste forms from the electrometallurgical treatment of sodium-bonded spent nuclear fuel

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Description

The ceramic and metal waste forms produced by electrometallurgical treatment of sodium-bonded spent nuclear fuel are undergoing evaluation as to how they will perform within the geologic repository which is proposed to be built at Yucca Mountain. An initial assessment, making use of preliminary degradation models for the waste forms, is described. The analyses are performed with a simplified version of the Total System Performance Assessment--Viability Assessment repository model. Results indicate that the ability of the ceramic and metal waste forms to retain radionuclides is similar to and sometimes better than defense high-level waste glass.

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10 p.

Creation Information

Morris, E. E.; Fanning, T. H.; Feldman, E. E. & Petri, M. C. March 20, 2000.

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  • Argonne National Laboratory
    Publisher Info: Argonne National Laboratory, Argonne, IL (United States)
    Place of Publication: Argonne, Illinois

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Description

The ceramic and metal waste forms produced by electrometallurgical treatment of sodium-bonded spent nuclear fuel are undergoing evaluation as to how they will perform within the geologic repository which is proposed to be built at Yucca Mountain. An initial assessment, making use of preliminary degradation models for the waste forms, is described. The analyses are performed with a simplified version of the Total System Performance Assessment--Viability Assessment repository model. Results indicate that the ability of the ceramic and metal waste forms to retain radionuclides is similar to and sometimes better than defense high-level waste glass.

Physical Description

10 p.

Notes

INIS; OSTI as DE00752873

Medium: P; Size: 10 pages

Source

  • ANS 4th Topical Meeting - DOE Spent Nuclear Fissile Material Management, San Diego, CA (US), 06/04/2000--06/08/2000

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  • Report No.: ANL/RA/CP-100483
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 752873
  • Archival Resource Key: ark:/67531/metadc711288

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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.

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Creation Date

  • March 20, 2000

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

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  • April 6, 2017, 6:54 p.m.

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Morris, E. E.; Fanning, T. H.; Feldman, E. E. & Petri, M. C. Repository performance assessment of waste forms from the electrometallurgical treatment of sodium-bonded spent nuclear fuel, article, March 20, 2000; Argonne, Illinois. (digital.library.unt.edu/ark:/67531/metadc711288/: accessed July 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.