Numerical studies of fluid and heat flow near high-level nuclear waste packages emplaced in partially saturated fractured tuff

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We have performed modeling studies on the simultaneous transport of heat, liquid water, vapor, and air in partially saturated fractured porous rock. Formation parameters were chosen as representative of the potential repository horizon in the Topopah Spring Unit of the Yucca Mountain tuffs. The presence of fractures makes the transport problem very complex, both in terms of flow geometry and physics. The numerical simulator "TOUGH" used for our flow calculations takes into account most of the physical effects which are important in multi-phase fluid and heat flow. It has provisions for handling the extreme non-linearities which arise in phase transitions, ... continued below

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51 p.

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Pruess, K.; Tsang, Y.W. & Wang, J.S.Y. November 1, 1984.

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Description

We have performed modeling studies on the simultaneous transport of heat, liquid water, vapor, and air in partially saturated fractured porous rock. Formation parameters were chosen as representative of the potential repository horizon in the Topopah Spring Unit of the Yucca Mountain tuffs. The presence of fractures makes the transport problem very complex, both in terms of flow geometry and physics. The numerical simulator "TOUGH" used for our flow calculations takes into account most of the physical effects which are important in multi-phase fluid and heat flow. It has provisions for handling the extreme non-linearities which arise in phase transitions, component disappearances, and capillary discontinuities at fracture faces. We model a region around an infinite linear string of nuclear waste canisters, taking into account both the discrete fractures and the porous matrix. From an analysis of the results obtained with explicit fractures, we develop equivalent continuum models which can reproduce the temperature, saturation, and pressure variation, and gas and liquid flow rates of the discrete fracture-porous matrix calculations. The equivalent continuum approach makes use of a generalized relative permeability concept to take into account the fracture effects. This results in a substantial simplification of the flow problem which makes larger scale modeling of complicated unsaturated fractured porous systems feasible. Potential applications for regional scale simulations and limitations of the continuum approach are discussed. 35 refs., 14 figs., 4 tabs.

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51 p.

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NTIS, PC A04/MF A01; OSTI as DE85010639

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  • Other Information: PBD: Nov 1984

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  • Other: DE85010639
  • Report No.: LBL--18552
  • Grant Number: AC03-76SF00098
  • DOI: 10.2172/60565 | External Link
  • Office of Scientific & Technical Information Report Number: 60565
  • Archival Resource Key: ark:/67531/metadc689956

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  • November 1, 1984

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  • Aug. 14, 2015, 8:43 a.m.

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  • April 5, 2016, noon

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Pruess, K.; Tsang, Y.W. & Wang, J.S.Y. Numerical studies of fluid and heat flow near high-level nuclear waste packages emplaced in partially saturated fractured tuff, report, November 1, 1984; California. (digital.library.unt.edu/ark:/67531/metadc689956/: accessed November 17, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.