Abstract
Validation and qualification of thermal-hydraulics system codes based on measured plant data are essential for their reliability when applied to nuclear power plant analyses. To this purpose, the Institute for Neutron Physics and Reactor Technology (INR) at the Karlsruhe Institute of Technology (KIT) is involved in various validation and qualification activities of different CFD, subchannel and system codes. This paper is focused on the application of multi-scale thermal-hydraulics approach (combination of subchannel and system codes) for the analysis of BWR transients such as the Anticipated Transients Without Scram (ATWS).A description of the thermal-hydraulics coupling methodology between ATHLET/COBRA-TF is given. The multi-scale thermal-hydraulics coupling was implemented inside the SALOME platform using the MEDCoupling interface and some of the NURESIM platform interpolators. Finally, the coupled ATHLET/COBRA-TF model for the Oskarshamn-2 NPP is presented and the main results of the ATWS transient analysis are discussed. The work was carried out in the frame of the European NURESAFE (NUclear REactor SAFEty Simulation Platform) project of the 7th EURATOM Framework Program, aimed at addressing the engineering aspects of nuclear safety of light water reactors.
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.
