Technical questions related to modeling ground water flow and radionuclide transport in unsaturated, fractured rock
Modeling Research Group 3 has identified a number of general areas for which technical questions remain unanswered. The group further ranked the areas in order of preceived importance. In each area a number of specific questions were raised and in some cases, a strategy was proposed to address those questions. The following issues and concerns are discussed: flow behavior in fractures and fracture/matrix interactions; model validation; need for new and improved modeling; treatment of uncertainty; scale effects; preferential pathways for flow and transport; scenario development and description;definition and treatment of model boundary conditions; treatment of system heterogeneity; experimentation related to modeling; engineering measures to improve performance of the natural barrier.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Regulatory Applications; Southwest Research Inst., San Antonio, TX (United States). Center for Nuclear Waste Regulatory Analyses; Arizona Univ., Tucson, AZ (United States). Dept. of Hydrology and Water Resources
- OSTI ID:
- 139531
- Report Number(s):
- NUREG/CP-0040; CONF-9101106-; ON: TI93016989; TRN: 94:007195
- Resource Relation:
- Conference: 5. flow and transport through unsaturated fractured rock related to high-level radioactive waste disposal, Tucson, AZ (United States), 7-10 Jan 1991; Other Information: PBD: Jun 1993; Related Information: Is Part Of Proceedings of workshop 5: Flow and transport through unsaturated fractured rock -- related to high-level radioactive waste disposal; Evans, D.D. [ed.] [Arizona Univ., Tucson, AZ (United States). Dept. of Hydrology and Water Resources]; Nicholson, T.J. [ed.] [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Regulatory Applications]; PB: 238 p.
- Country of Publication:
- United States
- Language:
- English
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