Attila Guba

Biography

The Thermohydraulic Laboratory has a great deal of experience in the thermohydraulic analysis of VVER type nuclear reactors in both experimental and computational areas. The experimental activity is based on the PMK-2 equipment, which is an integral model of the Paksi Nuclear Power Plant's primary and partly secondary circuit. Experiments and computer codes (RELAP5, ATHLET, and CATHARE) are used to perform the following tasks. Investigating accident and accident behavior of VVER-440 / V213 nuclear power plants, studying special problems (eg impact of non-condensing gases), developing potential accident management strategies for different accident situations (eg secondary "bleed and feed"). The laboratory participates in the American CAMP RELAP Users' Club, as well as the VVER-specific enhancement of CATHARE and ATHLET codes, including the combination of ATHLET and KIKO-3D three-dimensional neutron kinetic code. We are involved in the implementation of several accident management projects of the Paks Nuclear Power Plant through computer analyzes using the above codes. A thorough analysis was carried out for the Paks Nuclear Power Plant to investigate the effect of operative interventions needed in state-oriented accident management procedures. Our latest experiments demonstrated the effectiveness of some of the major accident management treatments. A thorough analysis was carried out for the Paks Nuclear Power Plant to investigate the effect of operative interventions needed in state-oriented accident management procedures. Our latest experiments demonstrated the effectiveness of some of the major accident management treatments. A thorough analysis was carried out for the Paks Nuclear Power Plant to investigate the effect of operative interventions needed in state-oriented accident management procedures. Our latest experiments demonstrated the effectiveness of some of the major accident management treatments.

Research Interest

Physics