Off-line Calibration Method of Differential Pressure Transmitter in Nuclear Power Plant

Abstract

The invention discloses an offline calibration method for a differential pressure transmitter of a nuclear power plant. The offline calibration method implemented under a normal temperature and normalpressure comprises: a flow display value of a differential pressure transmitter under a first working condition is read; a zero-point current of the differential pressure transmitter is measured; thedifferential pressure transmitter is checked to obtain a relationship between the differential pressure and current of the differential pressure transmitter under the normal temperature and pressure;a relationship between a differential pressure and a current of the differential pressure transmitter under a static pressure working condition is calculated; an actual differential pressure value and an actual current value under the first working condition are calculated; according to a target current value and the actual differential pressure value under the first working condition, a relationship between the differential pressure and the current of the differential pressure transmitter under the first working condition is determined; and on the basis of the relationship between the differential pressure and the current under the first working condition, the differential pressure transmitter is checked. With the offline calibration method, the differential pressure transmitter can be calibrated precisely in an offline state and the actual differential pressure parameter of working of the flow meter are determined accurately; the calibration environment becomes safe; and the calibration process is simplified.

Description

technical field [0001] The invention relates to the field of instrument calibration, in particular to an off-line calibration method for a nuclear power plant differential pressure transmitter. Background technique [0002] The pressurized water reactor nuclear power plant is mainly composed of a nuclear steam supply system (ie, the primary loop system), a steam turbine generator system (ie, the secondary loop system) and other auxiliary systems. PWR nuclear power plants use light water as the coolant. After the coolant absorbs the heat energy released by nuclear fuel fission in the core, it passes through the steam generator and then transfers the heat to the secondary circuit to generate steam, and then enters the steam turbine to do work, driving the generator to generate electricity. If the flow rate of the coolant loop in the primary circuit of the nuclear power plant is too high or too low, the production process will be affected, and it must be controlled within a re...

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Problems solved by technology

[0014] 3. During the online calibration process, it is necessary to read the dynamic current parameters of the meter to calculate the actual differential pressure range of the meter. However, due to the continuous operation of the primary circuit coolant, it is difficult to obtain accurate current measurement values, which will cause deviations in the range calculation

[0015] 4. During the online calibration process, it is necessary to isolate and adjust the instrument under static conditions, but if any of the isolation valves of the MD has a slight leak, the actual static differential pressure will change, which will greatly affect the accurate calibration of the instrument, resulting in calibration failure. failed or could not be calibrated

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