BLT-MS (Breach, Leach, and Transport -- Multiple Species) data input guide. A computer model for simulating release of contaminants from a subsurface low-level waste disposal facility

Sullivan, T.M.; Kinsey, R. R.; Aronson, A.; Divadeenam, M.; Mackinnon, Robert James

doi:10.2172/414349

Cited by 3 publications

(2 citation statements)

References 5 publications

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“…The Breach, Leach, and TransportMultiple Species (BLT-MS) code (Sullivan et al 1996) has been used to evaluate potential releases from a candidate disposal facility 6 . The BLT-MS code (which provides point-value estimates) was coupled with GoldSim to create a framework for 6 5 Examples of the types of problems to which GoldSim has been applied are listed at http://www.goldsim.com/ (accessed October 1, 2008).…”

Section: Snl Coupled Goldsim-blt-ms Software Packagementioning

confidence: 99%

Description of the Software and Integrating Platform

Flach¹

2009

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The Cementitious Barriers Partnership (CBP) Project is a multi-disciplinary, multi-institutional collaboration supported by the United States Department of Energy (US DOE) Office of Waste Processing. The objective of the CBP project is to develop a set of tools to improve understanding and prediction of the long-term structural, hydraulic, and chemical performance of cementitious barriers used in nuclear applications.A multi-disciplinary partnership of federal, academic, private sector, and international expertise has been formed to accomplish the project objective. In addition to the US DOE, the CBP partners are the Savannah River National Laboratory (SRNL), Vanderbilt University (VU) / Consortium for Risk The periods of cementitious performance being evaluated are >100 years for operating facilities and > 1000 years for waste management. The set of simulation tools and data developed under this project will be used to evaluate and predict the behavior of cementitious barriers used in nearsurface engineered waste disposal systems, e.g., waste forms, containment structures, entombments, and environmental remediation, including decontamination and decommissioning analysis of structural concrete components of nuclear facilities (spent-fuel pools, dry spent-fuel storage units, and recycling facilities such as fuel fabrication, separations processes). Simulation parameters will be obtained from prior literature and will be experimentally measured under this project, as necessary, to demonstrate application of the simulation tools for three prototype applications (waste form in concrete vault, high-level waste tank grouting, and spent-fuel pool). Test methods and data needs to support use of the simulation tools for future applications will be defined.The CBP project is a five-year effort focused on reducing the uncertainties of current methodologies for assessing cementitious barrier performance and increasing the consistency and transparency of the assessment process. The results of this project will enable improved risk-informed, performance-based decision-making and support several of the strategic initiatives in the DOE Office of Environmental Management Engineering & Technology Roadmap. Those strategic initiatives include 1) enhanced tank closure processes; 2) enhanced stabilization technologies; 3) advanced predictive capabilities; 4) enhanced remediation methods; 5) adapted technologies for site-specific and complex-wide D&D applications; 6) improved SNF storage, stabilization and disposal preparation; 7) enhanced storage, monitoring and stabilization systems; and 8) enhanced long-term performance evaluation and monitoring.

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Section: Snl Coupled Goldsim-blt-ms Software Packagementioning

confidence: 99%

Description of the Software and Integrating Platform

Flach¹

2009

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“…The accuracy of the source term data is often the most important factor affecting the overall accuracy of estimated risks associated with buried waste. Specialized source term codes such as Disposal Unit Source Term (DUST) (Sullivan 1993) and Breach, Leach, and Transport (BLT) (Sullivan et al 1996;Sullivan and Suen 1989; have been developed to generate source term input for the models. The models rely on empirically derived, lumped parameters (e.g., distribution coefficients) to describe important physical and chemical processes, reflecting the limited understanding of these processes.…”

Section: D3111 Summarymentioning

confidence: 99%

Deficiencies in Vadose Zone Understanding at the INEEL

Wood¹,

Bates²,

Bishop³

et al. 2000

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Waste Container and Waste Package Performance Modeling to Support Safety Assessment of Low and Intermediate-Level Radioactive Waste Disposal.

Sullivan¹

2004

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Prior to subsurface burial of low-and intermediate-level radioactive wastes, a demonstration that disposal of the wastes can be accomplished while protecting the health and safety of the general population is required. The long-time frames over which public safety must be insured necessitates that this demonstration relies, in part, on computer simulations of events and processes that will occur in the future. This demonstration, known as a Safety Assessment, requires understanding the performance of the disposal facility, waste containers, waste forms, and contaminant transport to locations accessible to humans. The objective of the coordinated research programme is to examine the state-of-the-art in testing and evaluation short-lived lowand intermediate-level waste packages (container and waste form) in near surface repository conditions.

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BLT-MS (Breach, Leach, and Transport -- Multiple Species) data input guide. A computer model for simulating release of contaminants from a subsurface low-level waste disposal facility

Cited by 3 publications

References 5 publications

Description of the Software and Integrating Platform

Description of the Software and Integrating Platform

Deficiencies in Vadose Zone Understanding at the INEEL

Waste Container and Waste Package Performance Modeling to Support Safety Assessment of Low and Intermediate-Level Radioactive Waste Disposal.

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