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

Conference · Sun Dec 31 04:00:00 EST 1995

OSTI ID:377958

McGrail, B P; Steefel, C I; Fort, J A; Engel, D W; Yabusaki, S B ^[1]

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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
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
A CODES
COMPUTERIZED SIMULATION
CONTAINERS
CONTAINMENT SYSTEMS
CORROSION
HAZARDOUS MATERIALS
HIGH-LEVEL RADIOACTIVE WASTES
LOW-LEVEL RADIOACTIVE WASTES
MITIGATION
PERFORMANCE
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE FACILITIES
RADIONUCLIDE MIGRATION
SAFETY ANALYSIS
WASTE FORMS
WATER INFLUX