Bending test device for mechanical integrity studies of spent nuclear fuel rods

Year

2016

Author(s)

Ramil Nasyrow - European Commission, Joint Research Centre, Institute for Transuranium Elements (ITU), Karlsruhe, Germany

Dimitrios Papaioannou - European Commission, Joint Research Centre, Institute for Transuranium Elements (ITU), Karlsruhe, Germany

V.V. Rondinella - European Commission, Joint Research Centre, Institute for Transuranium Elements (ITU), Karlsruhe, Germany

Efstathios Vlassopoulos - Swiss Federal Institute of Technology in Lausanne (EPFL), Switzerland

Konrad Linnemann - BAM Federal Institute for Materials Research and Testing

V. Ballheimer - BAM Federal Institute for Materials Research and Testing

Jens Sterthaus - BAM Federal Institute for Materials Research and Testing

Annette Rolle - BAM Federal Institute for Materials Research and Testing Berlin, Germany

Frank Wille - BAM Federal Institute for Materials Research and Testing

S. Caruso - National Cooperative for the Disposal of Radioactive Waste (NAGRA)

File Attachment

F6023.pdf1.01 MB

Abstract

This paper presents data obtained from experiments performed using a bending test set-up developed at the Joint Research Centre (JRC) – Karlsruhe, for spent fuel segment testing. Adjustable sample holders, loading modes and other experimental conditions can be implemented in the experiments to study the effects of different deformation ranges up to cladding failure. The experimental set-up has been adapted to hot cell remote controlling and has a modular configuration, which allows manual and motor-driven loading option. The device has been calibrated on hydrogenated, unirradiated cladding tube segments filled with alumina pellets. The final application of present set-up is to test non-defueled spent fuel rod segments, pressurized to the original spent fuel rod pressure level. The range of applicability of this device, the scope of the experimental program and the first results from actual bending tests will be discussed.