Thermal/fluid modeling of the response of saturated marine red clays to emplacement of nuclear waste

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This report discusses the heat and mass transport in marine red clay sediments being considered as a nuclear waste isolation medium. Development of two computer codes, one to determine temperature and convective velocity fields, the other to analyze the nuclide migration problem, is discussed and preliminary results from the codes reviewed. The calculations indicate that for a maximum allowable sediment/canister temperature range of 200 to 250/sup 0/C, the sediment can absorb about 1.5 kW initial power from waste in a 3 m long by 0.3 m diameter canister. The resulting fluid displacement due to convection is found to be small, ... continued below

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Pages: 22

Creation Information

McVey, D.F.; Gartling, D.K. & Russo, A.J. January 1, 1979.

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  • Sandia Laboratories
    Publisher Info: Sandia Labs., Albuquerque, NM (USA)
    Place of Publication: Albuquerque, New Mexico

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Description

This report discusses the heat and mass transport in marine red clay sediments being considered as a nuclear waste isolation medium. Development of two computer codes, one to determine temperature and convective velocity fields, the other to analyze the nuclide migration problem, is discussed and preliminary results from the codes reviewed. The calculations indicate that for a maximum allowable sediment/canister temperature range of 200 to 250/sup 0/C, the sediment can absorb about 1.5 kW initial power from waste in a 3 m long by 0.3 m diameter canister. The resulting fluid displacement due to convection is found to be small, less than 1 m. The migration of four nuclides, /sup 239/Pu, /sup 137/Cs, /sup 129/I, and /sup 99/Tc were computed for a canister buried 30 m deep in 60 m thick sediment. It was found that the /sup 239/Pu and /sup 137/Cs, which migrate as cations and have relatively high distribution coefficients, are essentially completely contained in the sediment. The anionic species, /sup 129/I and /sup 99/Tc, which have relatively low distribution coefficients, broke through the sediment in about 5000 years. The resultant peak injection rates which occur at about 15,000 years were extremely small (0.5 ..mu..Ci/year for /sup 129/I and 180 ..mu..Ci/year for /sup 99/Tc).

Physical Description

Pages: 22

Notes

Dep. NTIS, PC A02/MF A01.

Source

  • Workshop on the use of argillaceous materials for the isolation of radioactive wastes, Paris, France, 10 Sep 1979

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  • Report No.: SAND-79-1430C
  • Report No.: CONF-790938-2
  • Grant Number: EY-76-C-04-0789
  • Office of Scientific & Technical Information Report Number: 5964380
  • Archival Resource Key: ark:/67531/metadc1102822

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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, 1979

Added to The UNT Digital Library

  • Feb. 18, 2018, 3:59 p.m.

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  • March 11, 2019, 5:13 p.m.

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McVey, D.F.; Gartling, D.K. & Russo, A.J. Thermal/fluid modeling of the response of saturated marine red clays to emplacement of nuclear waste, article, January 1, 1979; Albuquerque, New Mexico. (https://digital.library.unt.edu/ark:/67531/metadc1102822/: accessed August 24, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.