The natural circulation experiments were performed in the Semiscale Mod-2A test facility, which is a small-scale model of the primary system of a four-loop Pressurized Water Reactor (PWR). The tests selected were Semiscale natural circulation tests S-NC-02 and S-NC-03. For sensitivity calculations, the latest RELAP5/MOD3.3 Patch05 computer code has been used. The ASCII input deck was obtained in the frame of RELAP5 code distribution for the auto validation purposes. The Symbolic Nuclear Analysis Package (SNAP) graphical user interface animation mask has been created to better understand the influence of varying interphase drag on natural circulation physical phenomena and processes. The results for S-NC-2 test showed that interphase drag coefficient has some influence on the mass flow during natural circulation, but smaller than suspected by code developers. For S-NC-3 test, it was confirmed that equating the height and distribution of the two-phase mixture in calculation within the U-tubes with the experimental condition is essential to correctly predict the heat transfer phenomena.
F.17 Transfer of existing technologies, know-how, methods and procedures into practice
COBISS.SI-ID: 32405287The project member is the national coordinator (for Slovenia) of the international research program US CAMP (Code Applications and Maintenance Program). In the program, which is devoted to the application and development of the thermal-hydraulic system code TRACE, used for analyses of thermal-hydraulic transients in nuclear power plants, more than 20 nuclear countries from all over the world are participating .
D.01 Chairing over/coordinating (international and national) projects
COBISS.SI-ID: 33090087The project leader is a permanent member of the program committee of the international conference "Nuclear Energy for New Europe" already from 2006 till 2020, where typically about 200 participants from more than 25 countries are participating.
D.03 Membership in foreign/international boards/committees
COBISS.SI-ID: 32521255