| 摘要 |
The present invention relates to a system for measuring a leakage rate of a containment building in a power operation of a nuclear power plant. The present invention aims to provide the system for measuring the leakage rate of the containment building in the power operation of the nuclear power plant, in which a leakage is measured by using a volume change of the containment building in a constant pressure state and an air supply state for an instrument without pressurizing the containment building in a normal power operation of the nuclear power plant. In order to achieve the object, the system of the present invention comprises: a volume change measurement unit which measures a volume change (ΔV) of the containment building by using a preset air volume of the containment building, a pressure change of the containment building measured through an inner manometer, and an inner temperature change of the containment building measured through a thermometer; an air flux calculation unit which calculates an air flux (Qcvp) for raising the pressure of the containment building to arbitrary pressure on the basis of the volume change (ΔV) measured through volume change measurement unit and a leakage rate measurement time (Δt); a reference state conversion unit which converts the air flux calculated through the air flux calculation unit into a reference state by using the pressure (mbar) and temperature (°K) of the containment building; and a leakage rate calculation unit which divides, by predetermined time, a difference between an air flux (Qair) for the instrument supplied through an air valve and pipe line for the instrument and the air flux (Qcvp.st) converted into the reference state through the reference state conversion unit and thus calculates an air leakage rate (Qcv1) of the containment building of the reference state. |
