New generation of CASTOR® casks for high enriched, high burn-up fuel from German NPP

Year
2004
Author(s)
Robert Gartz - GNS Gesellschaft für Nuklear-Service mbH/GNB
Bernhard Kühne - GNS Gesellschaft für Nuklear-Service mbH/GNB
Rudolf Diersch - GNS Gesellschaft für Nuklear-Service mbH/GNB
File Attachment
Abstract
Requirements for new cask designs for transport and long-term dry storage of spent fuel assemblies (FA) from LWR-reactors are based on both increased source terms of the LWR FA including MOX FA, as well as the demand for economical optimisation of decommissioning costs by increased cask capacities. For this, cask development is the challenge to create and establish cask designs that can accommodate more FA with higher source terms, each under fixed boundary conditions (i.e. transport requirements and limitations of the power plants as crane loads and/or fixed maximum dimensions). This task has been elaborated by working simultaneously on different development actions each focussed to improve the cask performance. In the following a brief summary will be presented to give an overview which developments and investigations have been and are still will be performed for development and safety analyses of the new CASTOR® -designs under the main subjects: material investigation and qualification, component tests and verifications, detailed design analysis and not at least design verification.