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

A steam generator and simulation test technology, applied in the testing of machines/structural components, measuring devices, instruments, etc., can solve the problems of huge energy consumption and low efficiency, and achieve precise temperature control, fast heating rate, and compact structure Effect

Active Publication Date: 2017-05-03
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

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

Method used

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

Examples

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Effect test

Embodiment 1

[0050] Example 1: Gap impurity concentration experiment

[0051] see figure 2 As shown in Table 1, it is a comparison chart / table of chloride ion concentrations in various parts of the circuit after 28 hours of concentration. When the stroke of the precision plunger pump is 20%, the flow rate is 12L / h, and the heat load is 2.68×105KJ / m 2 h. The temperatures of the preheater and the autoclave were 240°C and 280°C respectively, the pH was adjusted by morpholine to 9.6, and the chloride ion concentration of the bulk solution was 1mg / L. After 28 hours of concentration, the concentration factor is 1.75×10 4 times.

[0052] figure 2 In the middle abscissa, 28-1 refers to the concentration of impurity ions in the No. 1 (gap) sampling bottle after concentration for 28 hours, 28-2 is the concentration of impurity ions in the autoclave, 28-3 is the concentration of impurity ions in the sampling tank, 28- 4 is the concentration of impurity ions in the large water tank, and 28-4R ...

Embodiment 2

[0056] Example 2: Gap impurity return experiment

[0057] The working conditions of the experimental device for the preparation of the impurity return sample are: the pump stroke is 30%, the flow rate is 19.8L / h, the temperature of the preheater is 240°C, the temperature of the autoclave is 280°C, and the heat load of the experimental section is 2.49× 105KJ / m 2 h. The pH value was adjusted to 9.6 with morpholine, the concentration time was 24 hours, and the concentration factor was 2.67×10 4 times. After 24 hours of enrichment, the power supply of the experimental section was cut off immediately, and the temperature settings of the preheater and autoclave were lowered to 180°C (simulated reactor shutdown). Figure 3-6 In or shown in Table 2-5, 0h is the change of chloride ion concentration after the heating of the experimental section is stopped, and the preheater and autoclave are set at 180°C. 0.5h is the first rapid pressure change (4MPa-0.1MPa-4MPa), 5 seconds for pres...

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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...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G01M99/00
Inventor 胡石林彭德全张平柱王辉周洪毅
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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