CN112466488A - CPR1000 nuclear power unit SG simulation device and method - Google Patents

CPR1000 nuclear power unit SG simulation device and method Download PDF

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Publication number
CN112466488A
CN112466488A CN202011271300.5A CN202011271300A CN112466488A CN 112466488 A CN112466488 A CN 112466488A CN 202011271300 A CN202011271300 A CN 202011271300A CN 112466488 A CN112466488 A CN 112466488A
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China
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pressure
reaction kettle
pressure reaction
inner cavity
pipe
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CN202011271300.5A
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Chinese (zh)
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喻翠云
葛卫
黄志萍
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Nanhua University
University of South China
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Nanhua University
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/001—Mechanical simulators
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N1/00—Sampling; Preparing specimens for investigation
    • G01N1/02—Devices for withdrawing samples
    • G01N1/10—Devices for withdrawing samples in the liquid or fluent state
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N33/00—Investigating or analysing materials by specific methods not covered by groups G01N1/00 - G01N31/00
    • G01N33/18—Water
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N1/00—Sampling; Preparing specimens for investigation
    • G01N1/02—Devices for withdrawing samples
    • G01N1/10—Devices for withdrawing samples in the liquid or fluent state
    • G01N2001/1031—Sampling from special places
    • G01N2001/105—Sampling from special places from high-pressure reactors or lines
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Abstract

CPR1000 nuclear power unit SG analogue means and method relates to nuclear power equipment technical field. The CPR1000 nuclear power unit SG simulation device comprises a high-pressure reaction kettle, a pressure measuring device, a high-pressure sampler and a high-pressure feeder; the pressure measuring device is used for measuring the pressure in the inner cavity of the high-pressure reaction kettle; the high-pressure sampler is used for sampling a reagent in the inner cavity of the high-pressure reaction kettle; the high-pressure feeder is used for adding reagents into the inner cavity of the high-pressure reaction kettle. A method for researching water quality change of a CPR1000 nuclear power unit SG in a normal operation state is applied to the CPR1000 nuclear power unit SG simulation device, and comprises the following steps: 1, preparing test water; 2, preparing an experimental group and a control group; 3, the experiment of the experimental group and the control group was performed. The invention can simulate the temperature, pressure and liquid flowing state of the CPR1000 nuclear power unit SG in normal operation, and can be used for researching the water quality change condition of the CPR1000 nuclear power unit SG in the normal operation state.

Description

CPR1000 nuclear power unit SG simulation device and method
Technical Field
The invention relates to the technical field of nuclear power equipment, in particular to a device and a method for simulating an SG of a CPR1000 nuclear power unit.
Background
The CPR1000 nuclear power unit SG is essential key equipment in a nuclear power station water loop, the internal temperature of the nuclear power unit SG under normal operation is 280 ℃, the internal pressure is 6.7MPa, and the content is saturated vapor.
The research on the water quality change condition of the CPR1000 nuclear power unit SG in the normal operation state has very high necessity, and workers can conveniently know the scaling condition (scaling rate and scaling type) inside the CPR1000 nuclear power unit SG, so that a reference basis is provided for the use amount and the use time interval of a scale remover (polyacrylic acid) in the operation process of the CPR1000 nuclear power unit SG.
However, the CPR1000 nuclear power unit SG equipment is large in size, the difficulty of sample sampling operation of an operator is very high, multiple sampling needs to be performed at fixed time intervals in a related experiment for monitoring water quality change, the realization is more difficult, in addition, the time consumption of the related experiment for monitoring water quality change reaches hundreds of hours, and if the experiment is directly performed on the CPR1000 nuclear power unit SG, the normal operation of the whole nuclear power station is affected.
Therefore, the research and development of equipment which can simulate the normal operation of the CPR1000 nuclear power generating unit SG and can conveniently carry out experiments related to the change of the monitored water quality is urgently needed in the industry, but unfortunately, the equipment is not available in the industry at present.
Disclosure of Invention
The invention aims to overcome the defects of the prior art, provides a CPR1000 nuclear power unit SG simulation device and method, and solves the problem that the water quality change condition of the CPR1000 nuclear power unit SG in a normal operation state is difficult to study in the industry at present.
The technical scheme of the invention is as follows: the CPR1000 nuclear power unit SG simulation device comprises a high-pressure reaction kettle, a cooling coil, a heating device, a heat-insulating shell, a pressure measuring device, a high-pressure sampler and a high-pressure feeder;
an inner cavity is arranged in the high-pressure reaction kettle, and a normal-pressure charging opening is arranged at the upper end of the high-pressure reaction kettle;
the cooling coil is coiled in the inner cavity of the high-pressure reaction kettle, and two ends of the cooling coil extend out of the upper end of the high-pressure reaction kettle and are positioned outside the high-pressure reaction kettle;
the heating device is arranged on the outer wall of the high-pressure reaction kettle in an encircling manner;
the heat-insulating shell is arranged outside the heating device in an encircling manner;
the pressure measuring device is arranged on the high-pressure reaction kettle and is used for measuring the pressure in the inner cavity of the high-pressure reaction kettle;
the high-pressure sampler is arranged on the high-pressure reaction kettle and is used for sampling a reagent in the inner cavity of the high-pressure reaction kettle;
the high-pressure feeder is arranged on the high-pressure reaction kettle and is used for adding reagents into the inner cavity of the high-pressure reaction kettle.
The further technical scheme of the invention is as follows: it also comprises a stirring device; the stirring device comprises a driving part, a rotating shaft and a blade; the driving part is arranged outside the high-pressure reaction kettle and connected with the rotating shaft so as to drive the rotating shaft to rotate; one end of the rotating shaft is positioned in the inner cavity of the high-pressure reaction kettle, and the other end of the rotating shaft extends out of the upper end of the high-pressure reaction kettle and is connected with the driving part; the paddle is fixedly arranged on the rotating shaft and is positioned in the inner cavity of the high-pressure reaction kettle.
The invention further adopts the technical scheme that: the upper end of the high-pressure reaction kettle is provided with a guide outlet; the pressure measuring device comprises a delivery pipe and a pressure gauge; the lower end of the eduction tube extends into the inner cavity of the high-pressure reaction kettle through the eduction port, the upper end is positioned outside the high-pressure reaction kettle, and a shunt port is arranged on a tube body of the eduction tube positioned outside the high-pressure reaction kettle; the manometer is connected on the delivery pipe top end.
The further technical scheme of the invention is as follows: the upper end of the high-pressure reaction kettle is provided with a sampling port; the high-pressure sampler comprises a sampling main pipe, a sampling branch pipe, a manual valve A, a manual valve B and a manual valve C; the lower end of the sampling main pipe extends into the inner cavity of the high-pressure reaction kettle through the sampling port, and the upper end of the sampling main pipe is positioned outside the high-pressure reaction kettle and is in a horizontal extension state; the upper end of the sampling branch pipe is connected to a pipe section of the sampling main pipe, which is positioned outside the high-pressure reaction kettle and extends horizontally, and the lower end of the sampling branch pipe is used for discharging a sample; the manual valve A and the manual valve B are both arranged on a pipe section of the sampling main pipe, which is positioned outside the high-pressure reaction kettle and extends horizontally, and are positioned at two ends of the connection part of the sampling main pipe and the sampling branch pipe; and the manual valve C is arranged on the sampling branch pipe.
The further technical scheme of the invention is as follows: the upper end of the high-pressure reaction kettle is provided with a high-pressure charging opening; the high-pressure feeder comprises a material storage tank, a feeding pipe, a connecting pipe, a pressure release pipe, a manual valve D, a manual valve E and a manual valve F; the lower end of the material storage tank is provided with a feed opening, the upper end of the material storage tank is provided with a feed inlet, a connecting opening and a pressure release opening, and the feed inlet is provided with a sealing cover; the lower end of the charging pipe extends into the inner cavity of the high-pressure reaction kettle through a high-pressure charging opening, and the upper end of the charging pipe is connected with a charging opening at the lower end of the storage tank; one end of the connecting pipe is connected to a connecting port at the upper end of the material storage tank, and the other end of the connecting pipe is communicated with a flow dividing port on a pressure measuring pipe of the pressure measuring device; one end of the pressure release pipe is connected to the pressure release port at the upper end of the material storage tank, and the other end of the pressure release pipe is communicated with the external atmospheric pressure; the manual valve D is arranged on the feeding pipe; the manual valve E is arranged on the connecting pipe; the manual valve F is arranged on the pressure release pipe.
The further technical scheme of the invention is as follows: the upper end of the high-pressure reaction kettle is provided with a mounting port; the temperature measuring module is also included; the temperature measuring module comprises a temperature measuring tube and a platinum-rhodium thermocouple; the temperature measuring tube is a tube with an open upper end and a closed lower end, the lower end of the temperature measuring tube extends into the inner cavity of the high-pressure reaction kettle through the mounting port, the upper end of the temperature measuring tube is communicated with the external atmospheric pressure, and the tube cavity of the temperature measuring tube is not communicated with the inner cavity of the high-pressure reaction kettle; the platinum rhodium thermocouple is arranged in the tube cavity of the temperature measuring tube and is positioned in the inner cavity of the high-pressure reaction kettle.
The technical scheme of the invention is as follows: a method for researching water quality change of a CPR1000 nuclear power unit SG in a normal operation state is applied to the CPR1000 nuclear power unit SG simulation device, and comprises the following steps:
s01, preparation of test water: adding ammonia water into the first-grade water to adjust the pH to 9.4, and then adding 1ppm of Fe2O3And 1ppm of CaCO3Obtaining test water;
s02, preparation of experimental and control groups, respectively: preparing two sets of CPR1000 nuclear power unit SG simulation devices which are respectively used for experiments of an experimental group and a control group;
experimental groups: taking experimental water with the volume of 60 percent of the inner cavity of the high-pressure reaction kettle, adding the experimental water into the inner cavity of the high-pressure reaction kettle through a normal-pressure feeding port, and then adding 1ppm of polyacrylic acid ([ C ]3H4O2]n) As a dispersant to prevent scaling in the inner cavity of the high-pressure reaction kettle;
control group: taking experimental water with the volume of 60% of the inner cavity volume of the high-pressure reaction kettle, adding the experimental water into the inner cavity of the high-pressure reaction kettle through a normal-pressure feeding port, and adding no dispersing agent of any kind;
introducing nitrogen into the high-pressure reaction kettles of the experimental group and the control group to remove air, starting the stirring device to stir the blades at the speed of 1Hz, and then heating the experimental water to 280 ℃ by the heating device, and respectively starting timing when the saturated vapor pressure of water vapor reaches 6.7 Mpa;
s03, performing experiments of the experimental group and the control group, respectively: after timing, the experimental group and the control group sample the test water at intervals of a certain time and detect the concentrations of Fe and Ca elements, the test water with the same volume as the sample volume and the same concentration of the additive is supplemented after sampling each time to ensure that the water volume and the additive in the inner cavity of the high-pressure reaction kettle are kept constant, and a comparison graph of the change trend of the Fe element and the Ca element in the control group and the experimental group along with the time is drawn based on the detection result of the sample.
The further technical scheme of the invention is as follows: in the step S01, the temperature of the prepared test water was 25 ℃.
The further technical scheme of the invention is as follows: in step S03, for the experimental group, the additives are polyacrylic acid and Fe2O3And CaCO3For the experimental group, the additive was Fe2O3And CaCO3。
The further technical scheme of the invention is as follows: in the step S03, the total test duration of the control group and the test group is 500h, the control group and the test group are sampled once at an interval of 15min within 0-10h, the control group and the test group are sampled once at an interval of 1h within 10-20h, the control group and the test group are sampled once at an interval of 4h within 20-40h, the control group and the test group are sampled once at an interval of 8h within 40-100h, and the test group are sampled once at an interval of 24h within 100h and 500 h.
Compared with the prior art, the invention has the following advantages:
the device is formed by adding various functional parts into the existing high-pressure reaction kettle, can simulate the temperature, pressure and liquid flowing state of the CPR1000 nuclear power unit SG during normal operation, and can be used for researching the water quality change condition of the CPR1000 nuclear power unit SG during normal operation. Compared with the CPR1000 nuclear power unit SG, the device has low manufacturing cost and small volume, can realize on-line sealing sampling, sample adding, temperature measuring and pressure measuring without stopping midway, is convenient for carrying out related experiments for monitoring the water quality change, and thus provides reference basis for the use amount and the use time interval of a scale remover (polyacrylic acid) in the operation process of the CPR1000 nuclear power unit SG.
The invention is further described below with reference to the figures and examples.
Drawings
FIG. 1 is a schematic structural view of the present invention;
FIG. 2 is a cross-sectional view A-A of FIG. 1;
FIG. 3 is a top view of a high pressure reactor;
FIG. 4 is a graph comparing the change trend of Fe element with time in the control group and the experimental group;
fig. 5 is a graph comparing the change trend of Ca element with time in the control group and the experimental group.
Illustration of the drawings: a high-pressure reaction kettle 1; an inner cavity 10; a normal pressure feed inlet 11; a lead-out port 12; a sampling port 13; a high-pressure feed port 14; a mounting port 15; a cooling coil 2; a heating device 3; a heat-insulating shell 4; a pressure measuring device 5; a delivery pipe 51; a diversion port 511; a pressure gauge 52; a sampling main pipe 61; a sampling branch 62; manual valve a 63; manual valve B64; manual valve C65; a storage tank 71; a feed opening 711; a feed inlet 712; a coupling port 713; a pressure relief port 714; a feed tube 72; a coupling pipe 73; a pressure relief tube 74; manual valve D75; manual valve E76; manual valve F77; a driving member 81; a rotating shaft 82; a paddle 83; and a temperature measuring tube 91.
Detailed Description
Example 1:
as shown in fig. 1-3, the SG simulator of the CPR1000 nuclear power generating set comprises a high-pressure reaction kettle 1, a cooling coil 2, a heating device 3, a heat-preservation shell 4, a pressure measuring device 5, a high-pressure sampler, a high-pressure feeder, a stirring device and a temperature measuring module.
An inner cavity 10 is arranged in the high-pressure reaction kettle 1, and a normal-pressure feed inlet 11, a guide outlet 12, a sampling port 13, a high-pressure feed inlet 14 and a mounting port 15 are arranged at the upper end of the high-pressure reaction kettle 1.
The cooling coil 2 is coiled in the inner cavity of the high-pressure reaction kettle 1, and two ends of the cooling coil extend out of the upper end of the high-pressure reaction kettle 1 and are positioned outside the high-pressure reaction kettle 1.
The heating device 3 is arranged on the outer wall of the high-pressure reaction kettle 1 in an encircling manner.
The heat preservation shell 4 is arranged outside the heating device 3 in an encircling way.
The pressure measuring device 5 is installed on the high-pressure reaction kettle 1 and is used for measuring the pressure in the inner cavity of the high-pressure reaction kettle 1. The pressure measuring device includes a delivery tube 51 and a pressure gauge 52. The lower end of the leading-out pipe 51 extends into the inner cavity 10 of the high-pressure reaction kettle 1 through the leading-out port 12, the upper end is positioned outside the high-pressure reaction kettle 1, and the pipe body of the leading-out pipe 51 positioned outside the high-pressure reaction kettle 1 is provided with a flow dividing port 511. The pressure gauge 52 is connected to the upper end of the delivery pipe 51.
The high-pressure sampler is arranged on the high-pressure reaction kettle 1 and is used for sampling the reagent in the inner cavity 10 of the high-pressure reaction kettle 1. The high-pressure sampler comprises a main sampling pipe 61, a branch sampling pipe 62, a manual valve A63, a manual valve B64 and a manual valve C65. The lower end of the sampling main pipe 61 extends into the inner cavity 10 of the high-pressure reaction kettle 1 through the sampling port 13, and the upper end is positioned outside the high-pressure reaction kettle 1 and is in a horizontal extension state. The upper end of the sampling branch pipe 62 is connected to a pipe section of the sampling main pipe 61 extending horizontally outside the high-pressure reactor 1, and the lower end is used for discharging a sample. The manual valve A63 and the manual valve B64 are both arranged on a pipe section of the sampling main pipe 61, which is positioned outside the high-pressure reaction kettle 1 and extends horizontally, and are positioned at two ends of the connection part of the sampling main pipe 61 and the sampling branch pipe 62. A manual valve C65 is mounted on the sampling branch 62.
The high-pressure feeder is arranged on the high-pressure reaction kettle 1 and is used for adding reagents into an inner cavity 10 of the high-pressure reaction kettle 1. The high-pressure feeder comprises a storage tank 71, a feeding pipe 72, a connecting pipe 73, a pressure release pipe 74, a manual valve D75, a manual valve E76 and a manual valve F77. The lower end of the storage tank 71 is provided with a feed opening 711, the upper end of the storage tank 71 is provided with a feed opening 712, a coupling opening 713 and a pressure release opening 714, and the feed opening 712 is provided with a sealing cover. The lower end of the feed pipe 72 extends into the inner cavity 10 of the high-pressure reaction kettle 1 through the high-pressure feed port 14, and the upper end is connected with the feed port 711 at the lower end of the storage tank 71. One end of the connecting pipe 73 is connected to a connecting port 713 at the upper end of the material storage tank 71, and the other end of the connecting pipe is communicated with a flow dividing port on a pressure measuring pipe of a pressure measuring device. One end of the pressure release pipe 74 is connected to the pressure release port 714 at the upper end of the material storage tank 71, and the other end is communicated with the outside atmospheric pressure. A manual valve D75 is mounted on the fill tube 72. A manual valve E76 is mounted on the coupling pipe 73. A manual valve F77 is mounted on the relief tube 74.
The stirring device includes a driving member 81, a rotating shaft 82, and a paddle 83. The driving component 81 is installed outside the high-pressure reactor 1 and connected to the rotating shaft 82 to drive the rotating shaft 82 to rotate, specifically, the driving component 81 is a servo motor, and the servo motor is connected to the rotating shaft 82 through a pulley pair to drive the rotating shaft 82 to rotate. One end of the rotating shaft 82 is located in the inner cavity 10 of the autoclave 1, and the other end extends out from the upper end of the autoclave 11 and is connected with the driving part 81. The paddle 83 is fixedly installed on the rotating shaft 82 and is located in the inner cavity 10 of the autoclave 1.
The temperature measuring module includes a temperature measuring tube 91 and a platinum rhodium thermocouple (not shown). The temperature measuring tube 91 is a tube with an open upper end and a closed lower end, the lower end of the temperature measuring tube 91 extends into the inner cavity 10 of the high-pressure reaction kettle 1 through the mounting port 15, the upper end of the temperature measuring tube is communicated with the external atmospheric pressure, and the tube cavity of the temperature measuring tube 91 is not communicated with the inner cavity 10 of the high-pressure reaction kettle 1. The platinum rhodium thermocouple is arranged in the cavity of the temperature measuring tube 91 and is positioned in the inner cavity 10 of the high-pressure reaction kettle 1.
Briefly describing the working process of the invention:
the simulation device of the CPR1000 nuclear power unit SG can simulate the temperature, pressure and liquid flowing state of the CPR1000 nuclear power unit SG during normal operation, can realize on-line sealed sampling, sample adding, temperature measuring and pressure measuring without stopping midway, and is convenient for carrying out related experiments for monitoring water quality change.
1. The feeding method comprises the following steps:
when the SG simulation device of the CPR1000 nuclear power unit is used for the first time, a reagent can be added into the inner cavity 10 of the high-pressure reaction kettle 1 through the normal-pressure feed inlet 11. When the SG simulation device of the CPR1000 nuclear power unit operates, the pressure in the inner cavity 10 of the high-pressure reaction kettle 1 is far higher than the atmospheric pressure, and at the moment, if a reagent is added into the inner cavity 10 of the high-pressure reaction kettle 1, the reagent can be added through a high-pressure feeder. The adding method comprises the following steps: a. opening a manual valve F77 to discharge residual gas in the storage tank 71; b. opening a sealing cover on a feeding port 712 of the storage tank 71, adding the reagent into the storage tank 71, and discharging the air in the storage tank 71 to the outside through a pressure release pipe 74; c. after adding enough reagent, closing the sealing covers on the manual valve F77 and the feeding port 712, opening the manual valve D75 and the manual valve E76, so that the inner cavity of the storage tank 71 is communicated with the inner cavity 10 of the high-pressure reaction kettle 1, the pressure in the inner cavity of the storage tank 71 and the pressure in the inner cavity 10 of the high-pressure reaction kettle 1 become consistent, the reagent in the inner cavity of the storage tank 71 immediately flows downwards through the feeding pipe 72 to enter the inner cavity 10 of the high-pressure reaction kettle 1, and after the reagent enters the inner cavity 10 of the high-pressure reaction kettle 1, closing all the opened manual valves.
Note that: the manual valves which are not mentioned in the feeding method are all in a closed state in the whole process.
2. The pressure measuring method comprises the following steps:
when the SG simulation device of the CPR1000 nuclear power generating unit operates, the pressure gauge 53 is communicated with the inner cavity 10 of the high-pressure reaction kettle 1 through the eduction tube 51, the pressure in the inner cavity 10 of the high-pressure reaction kettle 1 can be known by directly reading the pressure gauge 52, and the pressure in the inner cavity 10 of the high-pressure reaction kettle 1 can be continuously monitored in the whole process.
Note that: the manual valves which are not mentioned in the pressure measuring method are all in a closed state in the whole process.
3. The online sampling method comprises the following steps:
when the SG simulation device of the CPR1000 nuclear power unit operates, in order to perform online sampling, firstly, a manual valve B64 is opened to enable a sample in the inner cavity 10 of the high-pressure reaction kettle 1 to enter a sampling main pipe 61, then, the manual valve B64 is closed, a manual valve A63 is opened to discharge a part of gas in the sampling main pipe 61, a manual valve C65 is opened to enable the sample to be discharged from the lower end of a sampling branch pipe 62, and finally, all the opened manual valves are closed.
Note that: the manual valves which are not mentioned in the online sampling method are all in a closed state.
Briefly describing the application of the invention:
the CPR1000 nuclear power unit SG simulation device can be used for researching the water quality change condition of the CPR1000 nuclear power unit SG in the normal operation state, and has the following operation steps:
s01, preparation of test water: adding ammonia water into the first-order water to adjust the pH value to 9.4,then 1ppm of Fe was added2O3And 1ppm of CaCO3Obtaining test water;
in this step, the temperature of the test water was 25 ℃.
S02, preparation of experimental and control groups, respectively: preparing two sets of CPR1000 nuclear power unit SG simulation devices which are respectively used for experiments of an experimental group and a control group;
experimental groups: taking experimental water with the volume of 60 percent of the inner cavity of the high-pressure reaction kettle, adding the experimental water into the inner cavity of the high-pressure reaction kettle through a normal-pressure feeding port, and then adding 1ppm of polyacrylic acid ([ C ]3H4O2]n) As a dispersant to prevent scaling in the inner cavity of the high-pressure reaction kettle;
control group: taking experimental water with the volume of 60% of the inner cavity volume of the high-pressure reaction kettle, adding the experimental water into the inner cavity of the high-pressure reaction kettle through a normal-pressure feeding port, and adding no dispersing agent of any kind;
introducing nitrogen into the high-pressure reaction kettles of the experimental group and the control group to remove air, starting the stirring device to stir the blades at the speed of 1Hz, and then heating the experimental water to 280 ℃ by the heating device, and respectively starting timing when the saturated vapor pressure of water vapor reaches 6.7 Mpa.
S03, performing experiments of the experimental group and the control group, respectively: after the test group and the control group are timed, the test water is sampled at intervals of a certain time, the concentrations of Fe and Ca elements are detected, the test water with the same volume as the sample volume and the same concentration as the additive is supplemented after each sampling so as to ensure that the water quantity and the additive in the inner cavity of the high-pressure reaction kettle are kept constant, and a comparison graph of the change trend of the Fe element and the Ca element in the control group and the test group along with the time is drawn based on the detection result of the sample (see fig. 4-5).
In the step, aiming at an experimental group, the additives are polyacrylic acid and Fe2O3And CaCO3For the experimental group, the additive was Fe2O3And CaCO3。
In the step, the total experiment duration of the control group and the experiment group is 500h, the control group and the experiment group are sampled once at an interval of 15min within 0-10h, the control group and the experiment group are sampled once at an interval of 1h within 10-20h, the control group and the experiment group are sampled once at an interval of 4h within 20-40h, the control group and the experiment group are sampled once at an interval of 8h within 40-100h, and the control group and the experiment group are sampled once at an interval of 24h within 100-500 h.
As shown in fig. 4, the line labeled "PAA dispersed" represents the course of the Fe concentration in the experimental group with time, and the line labeled "Blank" represents the course of the Fe concentration in the control group with time. As can be seen from FIG. 4, since PAA (polyacrylic acid) is added to the experimental group, the Fe concentration is relatively uniform in the early stage of the experiment, the fluctuation of the later concentration is relatively large, and PAA (polyacrylic acid) is not added to the control group, the fluctuation of the Fe concentration is relatively large in the early stage of the experiment, which indicates that PAA is used for Fe2O3Has a certain dispersion effect. When the experiment proceeded to the later stage, the Fe concentration in both the control and experimental groups fluctuated greatly due to PAA decomposition.
As shown in fig. 5, the line labeled "PAA dispersed" represents the course of the Ca concentration in the experimental group with time, and the line labeled "Blank" represents the course of the Ca concentration in the control group with time. As can be seen from FIG. 5, since PAA (polyacrylic acid) was added to the experimental group, the Ca concentration was relatively uniform in the early stage of the experiment and the fluctuation of the Ca concentration was relatively large in the later stage, and since PAA (polyacrylic acid) was not added to the control group, the fluctuation of the Ca concentration was relatively large in the whole course of the experiment, which indicates that PAA was responsible for CaCO3Has a certain dispersion effect. When the experiment proceeded to the later stage, the Ca concentration in both the control and experimental groups fluctuated greatly due to PAA decomposition.

Claims (10)

  1. The utility model provides a CPR1000 nuclear power generating set SG analogue means which characterized in that: comprises a high-pressure reaction kettle, a cooling coil, a heating device, a heat-insulating shell, a pressure measuring device, a high-pressure sampler and a high-pressure feeder;
    an inner cavity is arranged in the high-pressure reaction kettle, and a normal-pressure charging opening is arranged at the upper end of the high-pressure reaction kettle;
    the cooling coil is coiled in the inner cavity of the high-pressure reaction kettle, and two ends of the cooling coil extend out of the upper end of the high-pressure reaction kettle and are positioned outside the high-pressure reaction kettle;
    the heating device is arranged on the outer wall of the high-pressure reaction kettle in an encircling manner;
    the heat-insulating shell is arranged outside the heating device in an encircling manner;
    the pressure measuring device is arranged on the high-pressure reaction kettle and is used for measuring the pressure in the inner cavity of the high-pressure reaction kettle;
    the high-pressure sampler is arranged on the high-pressure reaction kettle and is used for sampling a reagent in the inner cavity of the high-pressure reaction kettle;
    the high-pressure feeder is arranged on the high-pressure reaction kettle and is used for adding reagents into the inner cavity of the high-pressure reaction kettle.
  2. 2. The CPR1000 nuclear power generating set SG simulator of claim 1, wherein: it also comprises a stirring device; the stirring device comprises a driving part, a rotating shaft and a blade; the driving part is arranged outside the high-pressure reaction kettle and connected with the rotating shaft so as to drive the rotating shaft to rotate; one end of the rotating shaft is positioned in the inner cavity of the high-pressure reaction kettle, and the other end of the rotating shaft extends out of the upper end of the high-pressure reaction kettle and is connected with the driving part; the paddle is fixedly arranged on the rotating shaft and is positioned in the inner cavity of the high-pressure reaction kettle.
  3. 3. The CPR1000 nuclear power generating set SG simulator of claim 2, wherein: the upper end of the high-pressure reaction kettle is provided with a guide outlet; the pressure measuring device comprises a delivery pipe and a pressure gauge; the lower end of the eduction tube extends into the inner cavity of the high-pressure reaction kettle through the eduction port, the upper end is positioned outside the high-pressure reaction kettle, and a shunt port is arranged on a tube body of the eduction tube positioned outside the high-pressure reaction kettle; the manometer is connected on the delivery pipe top end.
  4. 4. The CPR1000 nuclear power generating set SG simulator of claim 3, wherein: the upper end of the high-pressure reaction kettle is provided with a sampling port; the high-pressure sampler comprises a sampling main pipe, a sampling branch pipe, a manual valve A, a manual valve B and a manual valve C; the lower end of the sampling main pipe extends into the inner cavity of the high-pressure reaction kettle through the sampling port, and the upper end of the sampling main pipe is positioned outside the high-pressure reaction kettle and is in a horizontal extension state; the upper end of the sampling branch pipe is connected to a pipe section of the sampling main pipe, which is positioned outside the high-pressure reaction kettle and extends horizontally, and the lower end of the sampling branch pipe is used for discharging a sample; the manual valve A and the manual valve B are both arranged on a pipe section of the sampling main pipe, which is positioned outside the high-pressure reaction kettle and extends horizontally, and are positioned at two ends of the connection part of the sampling main pipe and the sampling branch pipe; and the manual valve C is arranged on the sampling branch pipe.
  5. 5. The CPR1000 nuclear power generating set SG simulator of claim 4, wherein: the upper end of the high-pressure reaction kettle is provided with a high-pressure charging opening; the high-pressure feeder comprises a material storage tank, a feeding pipe, a connecting pipe, a pressure release pipe, a manual valve D, a manual valve E and a manual valve F; the lower end of the material storage tank is provided with a feed opening, the upper end of the material storage tank is provided with a feed inlet, a connecting opening and a pressure release opening, and the feed inlet is provided with a sealing cover; the lower end of the charging pipe extends into the inner cavity of the high-pressure reaction kettle through a high-pressure charging opening, and the upper end of the charging pipe is connected with a charging opening at the lower end of the storage tank; one end of the connecting pipe is connected to a connecting port at the upper end of the material storage tank, and the other end of the connecting pipe is communicated with a flow dividing port on a pressure measuring pipe of the pressure measuring device; one end of the pressure release pipe is connected to the pressure release port at the upper end of the material storage tank, and the other end of the pressure release pipe is communicated with the external atmospheric pressure; the manual valve D is arranged on the feeding pipe; the manual valve E is arranged on the connecting pipe; the manual valve F is arranged on the pressure release pipe.
  6. 6. The CPR1000 nuclear power generating set SG simulator of any one of claims 1 to 5, wherein: the upper end of the high-pressure reaction kettle is provided with a mounting port; the temperature measuring module is also included; the temperature measuring module comprises a temperature measuring tube and a platinum-rhodium thermocouple; the temperature measuring tube is a tube with an open upper end and a closed lower end, the lower end of the temperature measuring tube extends into the inner cavity of the high-pressure reaction kettle through the mounting port, the upper end of the temperature measuring tube is communicated with the external atmospheric pressure, and the tube cavity of the temperature measuring tube is not communicated with the inner cavity of the high-pressure reaction kettle; the platinum rhodium thermocouple is arranged in the tube cavity of the temperature measuring tube and is positioned in the inner cavity of the high-pressure reaction kettle.
  7. 7. A method for researching water quality change of a CPR1000 nuclear power generating unit SG in a normal operation state is applied to the CPR1000 nuclear power generating unit SG simulation device of any one of claims 1-6, and is characterized by comprising the following steps:
    s01, preparation of test water: adding ammonia water into the first-grade water to adjust the pH to 9.4, and then adding 1ppm of Fe2O3And 1ppm of CaCO3Obtaining test water;
    s02, preparation of experimental and control groups, respectively: preparing two sets of CPR1000 nuclear power unit SG simulation devices which are respectively used for experiments of an experimental group and a control group;
    experimental groups: taking experimental water with the volume of 60 percent of the inner cavity of the high-pressure reaction kettle, adding the experimental water into the inner cavity of the high-pressure reaction kettle through a normal-pressure feeding port, and then adding 1ppm of polyacrylic acid ([ C ]3H4O2]n) As a dispersant to prevent scaling in the inner cavity of the high-pressure reaction kettle;
    control group: taking experimental water with the volume of 60% of the inner cavity volume of the high-pressure reaction kettle, adding the experimental water into the inner cavity of the high-pressure reaction kettle through a normal-pressure feeding port, and adding no dispersing agent of any kind;
    introducing nitrogen into the high-pressure reaction kettles of the experimental group and the control group to remove air, starting the stirring device to stir the blades at the speed of 1Hz, and then heating the experimental water to 280 ℃ by the heating device, and respectively starting timing when the saturated vapor pressure of water vapor reaches 6.7 Mpa;
    s03, performing experiments of the experimental group and the control group, respectively: after timing, the experimental group and the control group sample the test water at intervals of a certain time and detect the concentrations of Fe and Ca elements, the test water with the same volume as the sample volume and the same concentration of the additive is supplemented after sampling each time to ensure that the water volume and the additive in the inner cavity of the high-pressure reaction kettle are kept constant, and a comparison graph of the change trend of the Fe element and the Ca element in the control group and the experimental group along with the time is drawn based on the detection result of the sample.
  8. 8. The method for researching the water quality change of the CPR1000 nuclear power generating unit SG in a normal operating state as claimed in claim 7, wherein the method comprises the following steps: in the step S01, the temperature of the prepared test water was 25 ℃.
  9. 9. The method for researching the water quality change of the CPR1000 nuclear power generating unit SG in a normal operating state as claimed in claim 8, wherein the method comprises the following steps: in step S03, for the experimental group, the additives are polyacrylic acid and Fe2O3And CaCO3For the experimental group, the additive was Fe2O3And CaCO3。
  10. 10. The method for researching the water quality change of the CPR1000 nuclear power generating unit SG in a normal operating state as claimed in claim 9, wherein the method comprises the following steps: in the step S03, the total test duration of the control group and the test group is 500h, the control group and the test group are sampled once at an interval of 15min within 0-10h, the control group and the test group are sampled once at an interval of 1h within 10-20h, the control group and the test group are sampled once at an interval of 4h within 20-40h, the control group and the test group are sampled once at an interval of 8h within 40-100h, and the test group are sampled once at an interval of 24h within 100h and 500 h.
CN202011271300.5A 2020-11-13 2020-11-13 CPR1000 nuclear power unit SG simulation device and method Pending CN112466488A (en)

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JP2003156416A (en) * 2001-11-22 2003-05-30 Mitsubishi Heavy Ind Ltd Device and method for sampling high-pressure fluid
CN102426224A (en) * 2011-09-02 2012-04-25 清华大学 Tabulation simulation reactor and method for research on chemical stability of water quality of water supply network
CN204085938U (en) * 2014-08-22 2015-01-07 淄博正大节能新材料有限公司 Reactor on-line period device
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CN207085922U (en) * 2017-08-14 2018-03-13 江苏开放大学 A kind of permanent magnetism Stirring reactor
CN109078931A (en) * 2018-08-03 2018-12-25 西安热工研究院有限公司 The dynamic simulation tester and application method of high temperature gas cooled reactor nuclear power unit secondary circuit chemical cleaning
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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2003156416A (en) * 2001-11-22 2003-05-30 Mitsubishi Heavy Ind Ltd Device and method for sampling high-pressure fluid
CN102426224A (en) * 2011-09-02 2012-04-25 清华大学 Tabulation simulation reactor and method for research on chemical stability of water quality of water supply network
CN204085938U (en) * 2014-08-22 2015-01-07 淄博正大节能新材料有限公司 Reactor on-line period device
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