Abstract
This report is dealing with the influence of the cladding layer on linear elastic fracture mechanics analyses of reactor pressure vessels subjected to emergency core cooling situations. The American computer code OCA-I was modified in order to be able to solve the stress distribution produced by thermal and mechanical loading across an undisturbed cylinder wall which is composed of two different materials. A brief description of the analytical approach is given. Analyses of two typical loss-of-coolant accidents, the Large Break LOCA and the Small Break LOCA, in which long axial cracks have been assumed to exist prior to the transient were performed. The results are presented in form of comparisons between calculations without considering cladding effects, with thermal cladding effects included only, and with cladding accounted for in thermal as well as in stress analyses.
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.
