Mechanical modeling of nuclear waste disposal in argillite at the Nevada Test Site

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Numerical calculations for a near surface heater experiment in argillite conducted at the Nevada Test Site were performed using the finite element code ADINA assuming a two-dimensional axisymmetric geometry. The existence and extent of the region of tensional opening of joints surrounding the heater, predicted by the mechanical model, were confirmed by posttest borehole inspection, permeability measurements, and drillback. Exrapolation of near surface heater model to repository depths reveals the necessity for prior knowledge of the mechanical properties and state of stress in-situ. The extent of the joint opening zone, for example, is not altered by changes in the elastic … continued below

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4 p.

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Thomas, R. K. & Lappin, A. R. December 31, 1979.

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This article is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by the UNT Libraries Government Documents Department to the UNT Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 26 times. More information about this article can be viewed below.

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

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Numerical calculations for a near surface heater experiment in argillite conducted at the Nevada Test Site were performed using the finite element code ADINA assuming a two-dimensional axisymmetric geometry. The existence and extent of the region of tensional opening of joints surrounding the heater, predicted by the mechanical model, were confirmed by posttest borehole inspection, permeability measurements, and drillback. Exrapolation of near surface heater model to repository depths reveals the necessity for prior knowledge of the mechanical properties and state of stress in-situ. The extent of the joint opening zone, for example, is not altered by changes in the elastic modulus at the near surface, but is significantly decreased beyond certain depths depending upon the in-situ elastic modulus. Results of these calculations are presented. To further define the behavior at depth, and place bounds on the joint opening zone, far-field calculations were performed for a generic repository in argillite. Both spent fuel and high level waste heat sources were considered at different burial densities and depths. Results of a parametric study are presented in which the mechanical properties, in-situ stresses, and waste heat sources were varied.

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4 p.

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NTIS, PC A02/MF A01

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  • Materials Research Society annual meeting, LACES CONF-791173, MA (United States), 26-29 Nov 1979

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  • Report No.: SAND--79-1047C
  • Report No.: CONF-791112--3
  • Grant Number: EY-76-C-04-0789
  • Office of Scientific & Technical Information Report Number: 59384
  • Archival Resource Key: ark:/67531/metadc694250

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Office of Scientific & Technical Information Technical Reports

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  • December 31, 1979

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  • Aug. 14, 2015, 8:43 a.m.

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  • May 14, 2021, 9:04 a.m.

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Thomas, R. K. & Lappin, A. R. Mechanical modeling of nuclear waste disposal in argillite at the Nevada Test Site, article, December 31, 1979; Albuquerque, New Mexico. (https://digital.library.unt.edu/ark:/67531/metadc694250/: accessed May 27, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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