Thermohydraulic Department

The department has acquired important experience in the thermohydraulic analysis of VVER-type reactors, both in experimental and in analytical fields. The basis of the first one is the PMK-2, an integral-type scaled-down model of the primary and partly the secondary circuit of Paks NPP.

Experiments and computer codes (RELAP5, ATHLET and CATHARE) have been used:

to study the transient and accident behaviour of VVER-440/V213 plants

to study special problems (e.g. the effect of non-condensable gases)

to develop possible accident management strategies for various accident scenarios (e.g. secondary side bleed and feed).

The department participates in the RELAP Users' Club CAMP and in the VVER-specific development of the ATHLET and CATHARE codes, including the coupling of the 3D neutron kinetics code KIKO-3D with ATHLET.

. A number of the NPP's safety enhancement projects have been supported by computer analysis with the above codes. To support the development of symptom based emergency operating procedures for the Paks NPP the analysis of a wide range of accident scenarios has been performed.

The department has acquired important experience in the thermohydraulic analysis of VVER-type reactors, both in experimental and in analytical fields. The basis of the first one is the PMK-2, an integral-type scaled-down model of the primary and partly the secondary circuit of Paks NPP.

Experiments and computer codes (RELAP5, ATHLET and CATHARE) have been used:

to study the transient and accident behaviour of VVER-440/V213 plants

to study special problems (e.g. the effect of non-condensable gases)

to develop possible accident management strategies for various accident scenarios (e.g. secondary side bleed and feed).

The department participates in the RELAP Users' Club CAMP and in the VVER-specific development of the ATHLET and CATHARE codes, including the coupling of the 3D neutron kinetics code KIKO-3D with ATHLET.

Extended design basis accident analysis was performed for the safety reassessment of the Paks NPP in the framework of the AGNES project. A number of the NPP's safety enhancement projects have been supported by computer analysis with the above codes. To support the development of symptom based emergency operating procedures for the Paks NPP the analysis of a wide range of accident scenarios has been performed.