干旱区生态环境知识资源中心(Arid): Numerical studies of fluid and heat flow near high-level nuclear waste packages emplaced in partially saturated fractured tuff

Arid

DOI	10.2172/60565
报告编号	LBL--18552
来源ID	OSTI_ID: 60565
	Numerical studies of fluid and heat flow near high-level nuclear waste packages emplaced in partially saturated fractured tuff
	Pruess, K.; Tsang, Y.W.; Wang, J.S.Y.
英文摘要	We have performed modeling studies on the simultaneous transport of heat, liquid water, vapor, and air in partially saturated fractured porous rock. Formation parameters were chosen as representative of the potential repository horizon in the Topopah Spring Unit of the Yucca Mountain tuffs. The presence of fractures makes the transport problem very complex, both in terms of flow geometry and physics. The numerical simulator "TOUGH" used for our flow calculations takes into account most of the physical effects which are important in multi-phase fluid and heat flow. It has provisions for handling the extreme non-linearities which arise in phase transitions, component disappearances, and capillary discontinuities at fracture faces. We model a region around an infinite linear string of nuclear waste canisters, taking into account both the discrete fractures and the porous matrix. From an analysis of the results obtained with explicit fractures, we develop equivalent continuum models which can reproduce the temperature, saturation, and pressure variation, and gas and liquid flow rates of the discrete fracture-porous matrix calculations. The equivalent continuum approach makes use of a generalized relative permeability concept to take into account the fracture effects. This results in a substantial simplification of the flow problem which makes larger scale modeling of complicated unsaturated fractured porous systems feasible. Potential applications for regional scale simulations and limitations of the continuum approach are discussed. 35 refs., 14 figs., 4 tabs.
出版年	1984
报告类型	Technical Report
语种	英语
国家	美国
来源学科分类	58 GEOSCIENCES ; 05 NUCLEAR FUELS ; HIGH-LEVEL RADIOACTIVE WASTES ; RADIOACTIVE WASTE DISPOSAL ; TUFF ; POROSITY ; PERMEABILITY ; GROUND WATER ; NEVADA TEST SITE ; GEOLOGIC FISSURES ; COMPUTERIZED SIMULATION ; TEMPERATURE EFFECTS ; FLUID FLOW ; MATHEMATICAL MODELS ; GAS FLOW ; HEAT TRANSFER ; YUCCA MOUNTAIN ; Yucca Mountain Project
URL	http://www.osti.gov/scitech/servlets/purl/60565
资源类型	科技报告
条目标识符	http://119.78.100.177/qdio/handle/2XILL650/263660
推荐引用方式 GB/T 7714	Pruess, K.,Tsang, Y.W.,Wang, J.S.Y.. Numerical studies of fluid and heat flow near high-level nuclear waste packages emplaced in partially saturated fractured tuff,1984.