Abstract
A sudden and complete break is assumed close to the outlet nozzle of a pressurized water reactor and the accelerating flow is calculated within a slice taken from the upper plenum. The slice includes sections of the core support columns. An advanced boundary integral method is used for solution. Some results are checked by shallow water experiments. Based on the calculated pressure field, the transient loadings and deflections are determined for the sections of the core support columns. As an essential result, the fluid compressibility is found to be unimportant for calculation of the maximum structural response of the core support columns. This finding provides the basis for a three-dimensional analysis in part II of this paper. In addition, also the influence of other important assumptions and simplifications has been studied by several parameter variations.
Sign-in/Register to access full text options 
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.
