Transient calculations of coolant mixing in VVER-440/213 type RPV
19th Symposium of AER on VVER Reactor Physics and Reactor Safety (2009, Varna, Bulgaria)
Reactor Dynamics, Thermal Hydraulics and Safety Analysis, CFD Analysis
The Budapest University of Technology and Economics, Institute of Nuclear Techniques (BME NTI) has been working since 2001 on the three-dimensional CFD model of the reactor pressure vessel of the VVER-440 type reactors. During this time period ? due to the development of the available computational capacity ? a very complex and detailed model of the RPV has been developed.