Year-end Sale % OFF 
Abstract
The problems of fuel-cladding mechanical interaction are considered, and a survey is given of the causal processes in oxide fuel pins. Their importance is judged by relevant results from irradiation experiments in thermal and fast test reactors, and by corresponding modelling computations. It is demonstrated that critical cladding strain has to be expected only in case of large, fast rod power increase, primarily from reduced power to full power, and maybe also in case of serious cesium accumulation at the fuel/blanket interface. Steady-state fuel swelling does not make any considerable contribution to cladding strain by thermal creep or plastic flow.
Published Version
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
