PorSalsa User's Manual

Martinez, Mario J.; Hopkins, P.L.; Reeves, Paul C.

doi:10.2172/782712

Cited by 2 publications

(4 citation statements)

References 18 publications

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“…In the first case, a general expression for multiphase deformable fractured or porous media with saturations S is (e.g., Martinez et al 2001):…”

Section: Thermal Modelingmentioning

confidence: 99%

“…The set of Equations (3) and (4) are supplemented by expressions relating capillary pressure P c = P g -P l and relative permeability as a function of saturations. There are numerous models for these (see for example Pruess et al 1999or Martinez et al 2001) or van Genuchten (1980. Equations (3) and (4) can be cast in a variety of forms, depending on the choice of primary variables (i.e.…”

Section: Hydrologic Modelingmentioning

confidence: 99%

“…The sum on the right hand side is over the total possible N r homogeneous and heterogeneous reactions I r in , where ir  are the stoichiometric coefficients (number of moles of i participating in the rth reaction, Lichtner 1996; see Martinez et al 2001 for similar treatment). Let us consider only a single solute species, c, in a liquid phase, and account for advective and diffusive flux, wherein Equation (29) becomes:…”

Section: Radionuclide Decay and Retardationmentioning

confidence: 99%

See 2 more Smart Citations

Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC) : gap analysis for high fidelity and performance assessment code development.

Lee¹,

Siegel²,

Argüello³

et al. 2011

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This report describes a gap analysis performed in the process of developing the Waste Integrated Performance and Safety Codes (IPSC) in support of the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The goal of the Waste IPSC is to develop an integrated suite of computational modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with rigorous verification, validation, and software quality requirements.The gap analyses documented in this report were are performed during an initial gap analysis to identify candidate codes and tools to support the development and integration of the Waste IPSC, and during follow-on activities that delved into more detailed assessments of the various codes that were acquired, studied, and tested. The current Waste IPSC strategy is to acquire and integrate the necessary Waste IPSC capabilities wherever feasible, and develop only those capabilities that cannot be acquired or suitably integrated, verified, or validated.The gap analysis indicates that significant capabilities may already exist in the existing THC codes although there is no single code able to fully account for all physical and chemical iv processes involved in a waste disposal system. Large gaps exist in modeling chemical processes and their couplings with other processes. The coupling of chemical processes with flow transport and mechanical deformation remains challenging. The data for extreme environments (e.g., for elevated temperature and high ionic strength media) that are needed for repository modeling are severely lacking. In addition, most of existing reactive transport codes were developed for nonradioactive contaminants, and they need to be adapted to account for radionuclide decay and ingrowth. The accessibility to the source codes is generally limited. Because the problems of interest for the Waste IPSC are likely to result in relatively large computational models, a compact memory-usage footprint and a fast/robust solution procedure will be needed. A robust massively parallel processing (MPP) capability will also be required to provide reasonable turnaround times on the analyses that will be performed with the code.A performance assessment (PA) calculation for a waste disposal system generally requires a large number (hundreds to thousands) of model simulations to quantify the effect of model parameter uncertainties on the predicted repository performance. A set of codes for a PA calculation must be sufficiently robust and fast in terms of code execution. A PA system as a whole must be able to provide multi...

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“…In the first case, a general expression for multiphase deformable fractured or porous media with saturations S is (e.g., Martinez et al 2001):…”

Section: Thermal Modelingmentioning

confidence: 99%

Section: Hydrologic Modelingmentioning

confidence: 99%

Section: Radionuclide Decay and Retardationmentioning

confidence: 99%

See 1 more Smart Citation

Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC) : gap analysis for high fidelity and performance assessment code development.

Lee¹,

Siegel²,

Argüello³

et al. 2011

View full text Add to dashboard Cite

show abstract

“…For the H-12 work, we considered PorSalsa, a three-dimensional (3D), finiteelement (FE) based, nonisothermal flow and transport model, specifically developed for fast parallel computing (Martinez et al, 2001). The 3D model developed for the H-12 used nearly 10 6 FE nodes and the simulations were conducted on 20 nodes of a 36-node Linux-based cluster, with each simulation taking roughly six minutes to complete.…”

Section: Introductionmentioning

confidence: 99%

Long-Term Pumping Test at MIU Site, Toki, Japan: Hydrogeological Modeling and Groundwater Flow Simulation

Eliassi¹,

McKenna²

2003

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A conceptual model of the MIU site in central Japan, was developed to predict the groundwater system response to pumping. The study area consisted of a fairly large three-dimensional domain, having the size 4.24 x 6 x 3 km 3 with three different geological units, upper and lower fractured zones and a single fault unit. The resulting computational model comprised of 702,204 finite difference cells with variable grid spacing. Both steady-state and transient simulations were completed to evaluate the influence of two different surface boundary conditions: fixed head and no flow. Steady state results were used for particle tracking and also serving as the initial conditions (i.e., starting heads) for the transient simulations. Results of the steady state simulations indicate the significance of the choice of surface (i.e., upper) boundary conditions and its effect on the groundwater flow patterns along the base of the upper fractured zone. Steady state particle tracking results illustrate that all particles exit the top of the model in areas where groundwater discharges to the Hiyoshi and Toki rivers. Particle travel times range from 3.6x10 7 sec (i.e., ~1.1 years) to 4.4 x 10 10 sec (i.e., ~1394 years). For the transient simulations, two pumping zones one above and another one below the fault are considered. For both cases, the pumping period extends for 14 days followed by an additional 36 days of recovery. For the pumping rates used, the maximum drawdown is quite small (ranging from a few centimeters to a few meters) and thus, pumping does not severely impact the groundwater flow system. The range of drawdown values produced by pumping below the fault are generally much less sensitive to the choice of the boundary condition than are the drawdowns resulted from the pumping zone above the fault.5

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PorSalsa User's Manual

Cited by 2 publications

References 18 publications

Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC) : gap analysis for high fidelity and performance assessment code development.

Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC) : gap analysis for high fidelity and performance assessment code development.

Long-Term Pumping Test at MIU Site, Toki, Japan: Hydrogeological Modeling and Groundwater Flow Simulation

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