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Designing Shafts for Handling High-Level Radioactive Wastes in Mined Geologic Repositories

Douglas F. Hambley, John R. Morris

Nuclear Technology / Volume 80 / Number 3 / March 1988 / Pages 476-482

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT88-A34071

Waste package conceptual designs developed in the United States by the U.S. Department of Energy’s Office of Civilian Radioactive Waste Management are the basis for specifying the dimensions and weights of the waste package and transfer cask combinations to be hoisted in the waste handling shafts in mined geologic repositories for high-level radioactive waste. The hoist, conveyance, counterweight, and hoist ropes are then sized. Also taken into consideration are overwind and underwind arrestors and safety features required by the U.S. Nuclear Regulatory Commission. Other design features such as braking systems, chairing system design, and hoisting speed are considered in specifying waste hoisting system parameters for example repository sites.