Simulation of two-phase carbon-14 transport at Yucca Mountain, Nevada

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In support of pacific Northwest Laboratory`s (PNL) preliminary total system performance assessment of the proposed high-level nuclear-waste repository at Yucca Mountain, transport of carbon-14 (C{sup 14}) in the unsaturated zone was numerically modeled with the Multiphase Subsurface Transport Simulator (MSTS). Total system performance assessments are being conducted to estimate potential cumulative releases and doses from radionuclides being transported through different pathways to the accessible environment from the proposed waste repository. Transport of radionuclides in the gaseous and liquid phases are pathways through which some of the inventory in the proposed repository could reach the accessible environment. Carbon-14 transport in the ... continued below

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16 p.

Creation Information

White, M.D.; Freshley, M.D. & Eslinger, P.W. February 1, 1992.

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  • Pacific Northwest Laboratory
    Publisher Info: Pacific Northwest Lab., Richland, WA (United States)
    Place of Publication: Richland, Washington

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Description

In support of pacific Northwest Laboratory`s (PNL) preliminary total system performance assessment of the proposed high-level nuclear-waste repository at Yucca Mountain, transport of carbon-14 (C{sup 14}) in the unsaturated zone was numerically modeled with the Multiphase Subsurface Transport Simulator (MSTS). Total system performance assessments are being conducted to estimate potential cumulative releases and doses from radionuclides being transported through different pathways to the accessible environment from the proposed waste repository. Transport of radionuclides in the gaseous and liquid phases are pathways through which some of the inventory in the proposed repository could reach the accessible environment. Carbon-14 transport in the unsaturated zone at Yucca Mountain was estimated with MSTS by considering two-phase diffusion, advection, phase petitioning, and radioactive decay.Transport results were based on a two-dimensional physical and hydrogeological system that represented an east-west cross section through Yucca Mountain. Carbon-14 source rates from failed repository waste canisters were estimated from the source term modeling subtasks associated with PNL`s total system performance assessment of the proposed Yucca Mountain repository. Simulation results included estimates of liquid, gas, heat, and C{sup 14} transport within the unsaturated zone at Yucca Mountain. Predictions of C{sup 14} distributions surrounding the proposed nuclear waste repository within Yucca Mountain and a brief description of the thermal-hydrogeologic computer code MSTS are presented.

Physical Description

16 p.

Notes

INIS; OSTI as DE92010496

Source

  • National Water Wells Association (NWWA) meeting on solving ground water problems with models, Dallas, TX (United States), 11-13 Feb 1992

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  • Other: DE92010496
  • Report No.: PNL-SA--20324
  • Report No.: CONF-920256--2
  • Grant Number: AC06-76RL01830
  • Office of Scientific & Technical Information Report Number: 138387
  • Archival Resource Key: ark:/67531/metadc628273

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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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  • February 1, 1992

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

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  • April 7, 2016, 4:49 p.m.

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White, M.D.; Freshley, M.D. & Eslinger, P.W. Simulation of two-phase carbon-14 transport at Yucca Mountain, Nevada, article, February 1, 1992; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc628273/: accessed November 17, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.