A simulation test device for the concentration and return of impurities in steam generators of nuclear power plants

Abstract

The invention relates to a simulation test apparatus for impurity concentration and return of a nuclear power station steam generator. The apparatus comprises a voltage stabilization protection unit and is characterized by further comprising a high-pressure preheating unit and a circulation processing unit. The high-pressure preheating unit performs preheating and high pressure processing on a cooling liquid; the circulation processing unit reduces the temperature of high-temperature steam, converts the high-temperature steam into liquid water, directly filters various particle impurities in a loop, and adjusting the volume of the liquid; and the voltage stabilization protection unit carries out inflation protection on the loop. According to the invention, a pressure adjusting valve and a safety valve are additionally arranged in a loop system so that the system pressure adjusting speed and amplitude are controllable, and the return of the impurities is realized; the apparatus provided by the invention can simulate the research on the impurity concentration and return process of a nuclear power station steam generator heat-transfer pipe and a tube plate slit; the apparatus is compact in structure, less space is occupied, the motion is convenient, and the thermal efficiency is high; and the working temperature is 280 DEG C, the pressure scope is 0.1 to 6.5 MPa, and the thermal load of the heat-transfer pipe is 0 to 8.2*105 KJ / m<2>.h and is continuously adjustable.

Description

technical field [0001] The invention relates to a nuclear power plant simulation experiment device, in particular to a nuclear power plant steam generator impurity concentration and return simulation test device. Background technique [0002] The steam generator is one of the key equipment of the pressurized water reactor nuclear power plant. The heat transfer tube of the steam generator is the weakest link in the pressure boundary of the primary circuit. The heat transfer tube of the steam generator is easily affected by many factors such as design, manufacture and operation. However, the quality decline will cause deformation, failure or rupture of the heat transfer tube with a wall thickness of only about 1mm, causing the primary circuit radioactive medium to diffuse to the secondary circuit cooling system, resulting in the loss of water in the primary circuit of the reactor and forced to reduce power or even shut down the reactor, eventually resulting in radioactivity. S...

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Problems solved by technology

[0004] In laboratory research, the key is to simulate the energy exchange process between the primary loop and the secondary loop. The American Electric Power Research Institute (EPRI) and European nuclear energy research developed countries use water media with higher temperature and pressure in the heat transfer tube to simulate the primary loop and the secondary loop. The heat transfer of the loop, so the energy consumption is huge and the efficiency is very low

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