Abstract
The paper discusses the results of numerical assessment of LWR fuel bundle degradation phenomena during heating up in a flowing steam and top flooding with water under severe accident conditions that were investigated in the PARAMETER-SF1 test. The simulation was performed with the code SOCRAT that is widely used in Russia for safety assessment of VVER-type NPP under severe accident conditions. A set of interacting processes, including heat transfer, fuel liquefaction, oxidation of fuel rods claddings, melt relocation and oxidation, hydrogen generation is discussed. PARAMETER-SF1 was the first test in the PARAMETER program that comprised several tests with different configurations of the VVER bundle flooding (top, bottom, and combined). Investigation of the phenomenology during flooding of an overheated core at the early phase of severe accident when core keeps a mainly rod-like geometry is extremely important for understanding the possibilities and conditions for implementing the measures of severe accident management at LWR NPPs.
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.
