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Title: AREST-CT: A new chemical transport code for waste disposal system performance analysis

Conference ·
OSTI ID:377958
; ; ; ;  [1]
  1. Pacific Northwest Lab., Richland, WA (United States)

A new computer code, Analysis of Radionuclide Source-Term with Chemical Transport (AREST-CT), is described in this paper. The code is being designed to support performance assessment analyses of engineered systems for subsurface isolation of hazardous and radioactive wastes. Radionuclide releases from an engineered system are modeled by solving governing equations describing conservation of water mass, air mass, thermal energy, and chemical species mass. As such, the AREST-CT code will be capable of simulating radionuclide release and transport in a non-isothermal, unsaturated-saturated setting. Constitutive equations are implemented that describe corrosion of iron-based container materials, glass, and spent fuel waste forms. The governing equations are solved in a two-dimensional domain using an integrated finite-volume method. A third-order total variation diminishing (TVD) numerical scheme is evaluated to minimize numerical oscillations and dissipation of steep concentration gradients in advection-dominated transport problems.

DOE Contract Number:
AC06-76RL01830
OSTI ID:
377958
Report Number(s):
CONF-941075-; ISBN 1-55899-253-7; TRN: 96:025081
Resource Relation:
Conference: 18. international symposium on the scientific basis for nuclear waste management, Kyoto (Japan), 23-27 Oct 1994; Other Information: PBD: 1995; Related Information: Is Part Of Scientific basis for nuclear waste management 18. Part 1; Murakami, Takashi [ed.] [Ehime Univ., Matsuyama, Ehime (Japan). Dept. of Earth Sciences]; Ewing, R.C. [ed.] [Univ. of New Mexico, Albuquerque, NM (United States). Dept. of Earth and Planetary Sciences]; PB: 787 p.; Materials Research Society symposium proceedings, Volume 353
Country of Publication:
United States
Language:
English