ARDISC (Argonne Dispersion Code): computer programs to calculate the distribution of trace element migration in partially equilibrating media Metadata

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Title

  • Main Title ARDISC (Argonne Dispersion Code): computer programs to calculate the distribution of trace element migration in partially equilibrating media

Creator

  • Author: Strickert, R
    Creator Type: Personal
  • Author: Friedman, A M
    Creator Type: Personal
  • Author: Fried, S
    Creator Type: Personal

Contributor

  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization
    Contributor Info: USDOE

Publisher

  • Name: Argonne National Laboratory
    Place of Publication: Illinois

Date

  • Creation: 1979-04-01

Language

  • English

Description

  • Content Description: A computer program (ARDISC, the Argonne Dispersion Code) is described which simulates the migration of nuclides in porous media and includes first order kinetic effects on the retention constants. The code allows for different absorption and desorption rates and solves the coupled migration equations by arithmetic reiterations. Input data needed are the absorption and desorption rates, equilibrium surface absorption coefficients, flow rates and volumes, and media porosities.
  • Physical Description: 26 pages

Subject

  • Keyword: Desorption
  • Keyword: Elements
  • Keyword: Computer Codes
  • Keyword: Porous Materials
  • STI Subject Categories: 510300 -- Environment, Terrestrial-- Radioactive Materials Monitoring & Transport-- (-1989)
  • STI Subject Categories: 54 Environmental Sciences
  • Keyword: Waste Disposal
  • Keyword: Radionuclide Migration
  • Keyword: Simulation
  • Keyword: Materials
  • STI Subject Categories: 054000 -- Nuclear Fuels-- Health & Safety
  • STI Subject Categories: 12 Management Of Radioactive And Non-Radioactive Wastes From Nuclear Facilities
  • Keyword: A Codes
  • Keyword: Computerized Simulation
  • Keyword: Mass Transfer
  • Keyword: Waste Management 052002* -- Nuclear Fuels-- Waste Disposal & Storage
  • STI Subject Categories: 11 Nuclear Fuel Cycle And Fuel Materials
  • Keyword: Environmental Transport
  • Keyword: Radioactive Waste Disposal
  • Keyword: Management
  • Keyword: Adsorption
  • Keyword: Trace Amounts
  • Keyword: Sorption

Collection

  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report

Format

  • Text

Identifier

  • Report No.: ANL-79-25
  • Grant Number: W-31-109-ENG-38
  • DOI: 10.2172/6206257
  • Office of Scientific & Technical Information Report Number: 6206257
  • Archival Resource Key: ark:/67531/metadc1109574
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