A performance assessment methodology for high-level radioactive waste disposal in unsaturated, fractured tuff

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Sandia National Laboratories, has developed a methodology for performance assessment of deep geologic disposal of high-level nuclear waste. The applicability of this performance assessment methodology has been demonstrated for disposal in bedded salt and basalt; it has since been modified for assessment of repositories in unsaturated, fractured tuff. Changes to the methodology are primarily in the form of new or modified ground water flow and radionuclide transport codes. A new computer code, DCM3D, has been developed to model three-dimensional ground-water flow in unsaturated, fractured rock using a dual-continuum approach. The NEFTRAN 2 code has been developed to efficiently model radionuclide ... continued below

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Medium: P; Size: 43 p.

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Gallegos, D. P. July 1991.

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  • U.S. Nuclear Regulatory Commission
    Publisher Info: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering
    Place of Publication: United States
  • Sandia National Laboratories
    Publisher Info: Sandia National Labs., Albuquerque, NM (United States)
    Place of Publication: Albuquerque, New Mexico

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Description

Sandia National Laboratories, has developed a methodology for performance assessment of deep geologic disposal of high-level nuclear waste. The applicability of this performance assessment methodology has been demonstrated for disposal in bedded salt and basalt; it has since been modified for assessment of repositories in unsaturated, fractured tuff. Changes to the methodology are primarily in the form of new or modified ground water flow and radionuclide transport codes. A new computer code, DCM3D, has been developed to model three-dimensional ground-water flow in unsaturated, fractured rock using a dual-continuum approach. The NEFTRAN 2 code has been developed to efficiently model radionuclide transport in time-dependent velocity fields, has the ability to use externally calculated pore velocities and saturations, and includes the effect of saturation dependent retardation factors. In order to use these codes together in performance-assessment-type analyses, code-coupler programs were developed to translate DCM3D output into NEFTRAN 2 input. Other portions of the performance assessment methodology were evaluated as part of modifying the methodology for tuff. The scenario methodology developed under the bedded salt program has been applied to tuff. An investigation of the applicability of uncertainty and sensitivity analysis techniques to non-linear models indicate that Monte Carlo simulation remains the most robust technique for these analyses. No changes have been recommended for the dose and health effects models, nor the biosphere transport models. 52 refs., 1 fig.

Physical Description

Medium: P; Size: 43 p.

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INIS; OSTI as TI91015353

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  • Other Information: PBD: Jul 1991

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  • Other: TI91015353
  • Report No.: NUREG/CR--5701
  • Report No.: SAND--91-0539
  • Grant Number: AC04-76DP00789
  • DOI: 10.2172/138143 | External Link
  • Office of Scientific & Technical Information Report Number: 138143
  • Archival Resource Key: ark:/67531/metadc628299

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  • July 1991

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  • June 16, 2015, 7:43 a.m.

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  • April 7, 2016, 7:11 p.m.

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Gallegos, D. P. A performance assessment methodology for high-level radioactive waste disposal in unsaturated, fractured tuff, report, July 1991; United States. (digital.library.unt.edu/ark:/67531/metadc628299/: accessed September 23, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.