ABSTRACT
Radioactive nuclides moving with the fluid flow in fractured rocks is one of the most important safety issues of nuclear waste repositories. The nuclides are retarded by sorption and diffusion in and out of the rock matrix as well. Since 1970s, a large number of analytical, semi-analytical and numerical schemes were proposed to simulate transport process in single fracture, regular fracture network, and complicated random fracture network. These results provided important insights to understanding transport phenomenon in fractured crystalline rocks like granite. Berkowitz (2002), Neuman (2005) systematically reviewed the developments of modeling flow and transport in fractured geological medium in the past.
