Back-End Nuclear Fuel Cycle Options: Effects on High Level Waste Management and Disposal

Abstract

In this thesis, back end fuel cycle options for Pressurized Water Reactor are discussed in terms of effects on high level waste management and, more specifically, on geological disposal. Once-through and alternative closed nuclear fuel cycles for a typical Pressurized Water Reactor are compared with respect to waste disposal densities (waste disposal area required for spent fuel and high level waste) in a permanent geological repository and radiological toxicities of resultant wastes. In the first part of the study, utilizing the code MONTEBURNS, relevant compositions and decay heats of wastes generated in the considered fuel cycles are obtained for several selected burnup values. Then, using the code ANSYS, thermal analyses are performed for a reference repository concept and disposal areas needed for waste types under consideration are determined.