Salt disposal of heat-generating nuclear waste.

摘要: This report summarizes the state of salt repository science, reviews many technical issues pertaining to disposal heat-generating nuclear waste in salt, and proposes several avenues for future science-based activities further basis salt. There are extensive formations forty-eight contiguous states, them may be worthy consideration disposal. The United States has experience sciences, including an operating facility transuranic wastes. scientific background laboratory field tests at ambient elevated temperature, principles behavior, potential fracture damage its mitigation, seal systems, chemical conditions, advanced modeling capabilities near-future developments, performance assessment processes, international collaboration all discussed. discussion is brought current, a summary recent workshops dedicated high-level Lessons learned from Sandia National Laboratories' on Waste Isolation Pilot Plant Yucca Mountain Project as well related with Strategic Petroleum Reserve applied this assessment. Disposal suitable formation attractive because material essentially impermeable, self-sealing, thermally conductive. Conditions chemically beneficial, significant base exists understanding environment. Within period institutional control, overburden pressure will fractures provide setting that limits radionuclide movement. A could potentially achieve total containment, no releases environment undisturbed scenarios long region geologically stable. Much gained development, such system design, coupled process simulation, application methodology, helps define clear strategy