Instrucment Of Containment System Leakage Test Development And Application

The nuclear power was taken as a clean energy, which produces the massive electric powers for the humanity, but accompanied by unwanted radioactivity. The Containment of nuclear power station as a final barrier to ensure public safety, which must through the Containment system leakage test to prove that the Containment can prevent the radiation leak to external environment effectively.The instrument studied in this paper is aims at the Containment system leakage test of nuclear power station. This instrument controlled by SCM measures the physical quantities of the measured object, such as pressure, flow, temperature and so on, and the measured data was displayed in LCD. This instrument connected to upper computer (PC) analyses the measured data according to the least square method. Based on the related statutes, standards, and the historical measured data of the same object, the instrument evaluates the leakage rate and saves the measured data to the historical measured data.What this paper studies is the development of software and hardware in this instrument, which have the functions of measurement, data display, autochangeover range, data accumulative total and the sensor zero seted, etc. And the software of notebook computer taken as upper computer can analyze data, judge and save the result.The software system of this instrument was developed by assemble language of C51. The software system of the upper compute which connected to the instrument was developed by Agilent VEE that is a graphical programming environment. The hardware control system of the instrument was composed by the SCM, the keyboard chip, the flow sensor, the pressure sensor, the analog-to-digital converter, the temperature sensor, CMOS real-time clock, LCD, etc. The hardware gas system of the instrument was composed by the filter, the reducing valve, the four-way globe valve, the three-way globe valve, the stop valve, the pressurization tube, and so on.