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Transport parameters in bentonite and candidate repository host rocks

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:5092019
Transport parameters (diffusion coefficients D({theta}), hydraulic conductivities K({theta}), and retardation factors R{sub f}) are being experimentally determined in materials relevant to the proposed high-level nuclear waste repository in Japan. The materials are compacted bentonite, which will be used as a backfill material around the canisters, and whole rock from the four candidate host rock environments (granite, basalt, tuff, and mudstone). Knowledge of D({theta}) and K({theta}) as a function of the volumetric water content {theta} is particularly important in the near-field transition zone around waste packages where changes in temperature, water content and composition, compaction of backfill, infiltration of fines, and secondary mineralization will alter the transport character of near-field environments. The transport parameters are being investigated using a new flow technology, the Unsaturated Flow Apparatus (UFA{trademark}), that overcomes some of the experimental difficulties involved with investigating low-conductivity materials by combining the larger driving forces obtainable with centrifugation techniques with precision fluid flow through a rotating seal. Once the water content is fixed at the target value and the system has achieved hydraulic steady state, transport parameters are determined from associated methods.
OSTI ID:
5092019
Report Number(s):
CONF-911107--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 64
Country of Publication:
United States
Language:
English