Testing system for studying dead tube section phenomenon of nuclear power plant

Abstract

The invention provides a testing system for studying a dead tube section phenomenon of a nuclear power plant. The testing system comprises a dead tube section and a first mechanism, wherein the first mechanism is used for simulating internal temperature of the dead tube section; the dead tube section is a completely sealed metal pipeline; a liquid inlet and a liquid outlet are formed in the dead tube section; the first mechanism comprises a convection tube, a heater, far heat transfer electrical resistance thermometers, magnetic turnover plate liquidometers and a first far heat transfer differential pressure transmitter; the convection tube is a completely sealed metal pipeline and forms a communicated first loop with the dead tube section through two pipelines; an exhaust hole is formed in the convection tube; the heater is connected with the dead tube section to achieve liquid heating treatment; a plurality of far heat transfer electrical resistance thermometers are respectively mounted on the dead tube section and the convection tube; one of two magnetic turnover plate liquidometers is mounted on the dead tube section; the other one of the two magnetic turnover plate liquidometers is mounted on the convection tube; and the first far heat transfer differential pressure transmitter is mounted on the dead tube section and is serially connected with the dead tube section to form a second loop. By adopting the testing system, the dead tube section phenomenon can be studied and discussed by using testing simulation technical measures, and in addition the testing system is reasonable and reliable in design.

Description

technical field [0001] The invention relates to the technical field of nuclear power safety measurement, in particular to a test system for researching dead pipe section phenomena in nuclear power plants. Background technique [0002] There is a restricted space in the interface area between the safety injection system RIS and the reactor coolant system RCP. The liquid is not in a macroscopic static state, so the pipeline is usually called a RIS dead pipe section. [0003] When the nuclear power plant is in normal operation, the side of the RIS dead pipe close to the RCP is often heated by the RCP coolant (the temperature can reach 320°C), so that the wall surface of the check valve disc on this side is often corroded, resulting in damage to the sealing performance of the valve. People often refer to this kind of corrosion phenomenon as dead pipe phenomenon. However, the existence of the dead pipe phenomenon directly threatens the reliability of the second safety barrier o...

AI Technical Summary

Problems solved by technology

However, the existence of the dead pipe phenomenon directly threatens the reliability of the second safety barrier of nuclear power plants.

However, over the years, although the nuclear industry at home and abroad has conducted a lot of theoretical research, there is still no feasible test method to completely simulate the real operating conditions of nuclear power plants.

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