Measurement of the coolant flow in the primary circuit of the VVER 1000/320 reactor is based on the measurement of the pressure drop either on the main circulation pump, [...]

Integrity of the VVER reactors internals is the important requirement of the NPPs long term operation. Two possible methods how to meet these requirements are: non destru [...]

The theoretical model is presented. The vibrations are proposed to be random nature and are caused by random pressure fluctuation in the turbulent boundary layer surround [...]

On the basis of electromechanical analogy is as criterion of possible interaction of acoustic waves in primary circuit of NPP Temelin derived so-called quality factor Q. [...]

Licensing of new NPPs is every deterministic. The same is valid for design of all safety related components. Probabilistic methods represent good tool for decision making [...]

An analysis model has been drived on the vibrations of fuel rod induced by coolant cross flow in the reactor core. The force on the fuel rod was fitted out using paramete [...]

Historically, the safety of nuclear power plants (NPPs) is based on the ability to eliminate the large loss-of-coolant accident (large LOCA) which is represented by the d [...]