DEEP BOREHOLE DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTE
Analyses show that granite bedrock temperatures near the disposal borehole would increase to a peak about 30o C above ambient conditions for the disposal of a string of spent nuclear fuel assemblies and by about 120o C for vitrified high-level waste from fuel reprocessing. Coupled thermal-hydrologic modeling indicates transient upward specific discharge of about 1.5 cm/yr from the thermal expansion of groundwater, which dissipates within several hundred years of waste emplacement. Preliminary analyses of nuclear criticality, molecular diffusion, and thermally induced hydrofracturing of the bedrock suggest that none of these processes would have significant impacts on safety of the disposal system. Preliminary modeling of performance assessment that includes solubility, sorption, groundwater transport, and shallow aquifer pumping indicates that dose to a hypothetical human receptor would be limited to a single radionuclide (Iodine-129) and would be negligible.
Several technical issues related to the deep borehole disposal of radioactive waste are being investigated in greater detail, including: 1) modeling of the coupled thermal-hydrologic-chemical-mechanical behavior near the borehole, 2) long-term behavior of seals, 3) deployment of compounds that sorb/sequester radioactive iodine in the borehole or seals and 4) more detailed performance assessment analyses.