CN103822792A - Simulation test apparatus for impurity concentration and return of nuclear power station steam generator - Google Patents
Simulation test apparatus for impurity concentration and return of nuclear power station steam generator Download PDFInfo
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- CN103822792A CN103822792A CN201310699004.9A CN201310699004A CN103822792A CN 103822792 A CN103822792 A CN 103822792A CN 201310699004 A CN201310699004 A CN 201310699004A CN 103822792 A CN103822792 A CN 103822792A
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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
The present invention relates to a kind of Nuclear Power Plant Simulation experimental provision, relate in particular to a kind of nuclear power station steam generator impurity of the present invention and concentrate and the simulation test device returning.
Background technology
Steam generator is one of key equipment of pressurized-water reactor nuclear power plant, steam generator heat-transfer pipe is the weak link the most on a circuit pressure border, steam generator heat-transfer pipe is easily subject to the impact of the factors such as design, manufacture and operation to occur defect and quality declines, cause the only distortion of the heat-transfer pipe about 1mm of wall thickness, lost efficacy or broke, cause a loop radiating medium to be diffused into secondary circuit cooling system, cause reactor-loop dehydration and be forced to reduce even shutdown of power, finally cause radiomaterial to be discharged into the major accident in environment; The reliability of visible steam generator heat-transfer pipe directly has influence on reliability, security and the economy of reactor operation.
US Westinghouse company (Westinghouse) shows the statistics of nuclear power station steam generator heat-transfer pipe breakage in recent years, and more than 70% nuclear power station steam generator heat-transfer pipe corrosion and damage is all to cause because the impurity of slit region between steam generator heat-transfer pipe and tube sheet concentrates.Steam generator working group (SGOG) has been set up in American Electric Power research institute (EPRI) and Class PWR Plants cooperation, according to the crevice corrosion problem occurring in nuclear power station steam generator operational process, carry out effective research, grasp the rule that gap impurity concentrates, develop gap impurity return technique, utilized in the process of maintenance period downrating of reloading and implement gap impurity return technique.
In laboratory study, it is crucial simulating a loop and secondary circuit energy exchange processes, American Electric Power research institute (EPRI) and European nuclear energy research developed country adopts the heat transfer that passes into aqueous medium that temperature, pressure is higher in heat-transfer pipe and simulate a loop and secondary circuit, therefore energy charge is huge, and efficiency is very low.In the present invention, adopt electrically heated rod to carry out direct modeling one loop thermal source, energy efficiency is high, and the rate of heat addition is fast.Secondary circuit moisturizing enters autoclave (model steam generator secondary side) after being heated to design temperature by primary heater, in adopting, the mode of heating is directly to the water heating in primary heater, firing rate is fast, and temperature control is accurate, accurately adjustable continuously in the temperature range needing at us.
In view of above-mentioned defect, creator of the present invention has obtained this creation finally through long research and practice.
Summary of the invention
The object of the present invention is to provide a kind of nuclear power station steam generator impurity to concentrate with the simulation test device returning in order to overcome above-mentioned technological deficiency.
For achieving the above object, the invention provides a kind of nuclear power station steam generator impurity of the present invention and concentrate and the simulation test device returning, it comprises a voltage-stabilizing protection unit, and it also comprises a high pressure preheating unit and a circular treatment unit; Wherein,
Described high pressure preheating unit comprises a double-tube heat exchanger, and cooling liquid is carried out thermal pretreatment by the high temperature high pressure liquid that described double-tube heat exchanger utilizes described high pressure preheating unit to produce, then the liquid after described thermal pretreatment is carried out to HIGH PRESSURE TREATMENT;
Described circular treatment unit comprises that a cooling filtering device, an aqueous water pump into device and a voltage stabilizing snubber assembly; Described cooling filtering device is in order to become the various granule foreigns in aqueous water and filtration circuit by the water vapor cooling of high temperature; Described aqueous water pumps into device in order to normal temperature low-pressure liquid water is become to normal temperature high voltage aqueous water, then pumps in described double-tube heat exchanger; Described voltage stabilizing snubber assembly is in order to adjust the volume of aqueous water in loop;
Described voltage-stabilizing protection unit comprises a gas cylinder, and described gas cylinder is connected with circular treatment unit with described high pressure preheating unit by a stop valve respectively.
Preferably, described high pressure preheating unit also comprises an autoclave and a primary heater, described autoclave is connected with described double-tube heat exchanger by a stop valve, and described double-tube heat exchanger is connected with described primary heater front end, and described primary heater rear end is connected with described autoclave by a stop valve;
The flow through outer tube of described double-tube heat exchanger of high temperature high pressure liquid in described autoclave, will send into primary heater after the water heating in double-tube heat exchanger inner tube, and primary heater is sent the water after preheating into circular treatment in autoclave again; Described double-tube heat exchanger outer tube is connected with described cooling filtering device.
Preferably, described cooling filtering device comprises a refrigeratory and a filtrator;
Described refrigeratory is in order to become aqueous water by the water vapor cooling of high temperature, and described filtrator is in order to directly to filter out the various granule foreigns in loop; Between described refrigeratory and described filtrator, have a safety feature, described safety feature is in order to adjust the pressure of controlling whole circuit system.
Preferably, described circular treatment unit also comprises a collecting box, for to loop liquid sampling; The water inlet end of described collecting box is connected with the water outlet end of described voltage stabilizing snubber assembly.
Preferably, described aqueous water pumps into device and is connected with the water outlet end of collecting box, in order to normal temperature low-pressure water process is become to normal temperature high voltage water, then pumps in described double-tube heat exchanger inner tube.
Preferably, described gas cylinder comprises nitrogen cylinder and helium tank, and described nitrogen cylinder is in order to loop deoxygenation, and described helium tank is with thinking that the experimental section in described autoclave fills helium.
Preferably, the condition of work that described experimental provision impurity concentrates is for being: precision plunger pump stroke is 20%, and flow is 12L/h, and thermal load is 2.68 × 105KJ/m
2h, the temperature of primary heater and autoclave is respectively 240 ℃ and 280 ℃, and it is 9.6 that morpholine regulates pH, and bulk solution chlorine ion concentration is 1mg/L.
Preferably, concentrating in technique of described impurity, the computing formula of concentration factor is:
F=40(c1-c2)/0.364，
In formula, F is impurity concentration factor, and 40 are fixed as 40mL for each sample volume, and 0.364 is gap volume 0.364mL, and c1 is the concentration impurity ion in sampling jar, and c2 is concentration impurity ion in autoclave.
Preferably, the condition of work that described experimental provision impurity returns to the preparation of sample is: pump stroke is 30%, and flow is 19.8L/h, and primary heater temperature is 240 ℃, and autoclave temp is 280 ℃, and experimental section thermal load is 2.49 × 105KJ/m2h; Concentrating after 24 hours, cutting off experimental section power supply, the desired temperature of primary heater and autoclave is being reduced to 180 ℃ simultaneously.
Preferably, returning in technique of described impurity, the computing formula that impurity returns to efficiency eta is:
η=(k1-k2)/k1
In formula, k1 is for returning to concentration impurity ion in the sampling jar of front gap, and k2 is for returning to after technique concentration impurity ion in the sampling jar of gap.
Beneficial effect of the present invention is compared with the prior art:
The present invention adopts electrically heated rod to carry out direct modeling one loop thermal source, and energy efficiency is high, and the rate of heat addition is fast; In circuit system, increased pressure regulator valve and safety valve, system pressure governing speed and amplitude are controlled, realize returning of impurity; Beneficial effect also comprises following 4 points:
(1) apparatus of the present invention can be simulated nuclear power station steam generator heat-transfer pipe and tube sheet gap impurity concentrates and returns to technical study;
(2) apparatus of the present invention compact conformation, takes up room little, conveniently moving, and the thermal efficiency is high;
(3) apparatus of the present invention working temperature can reach 300 ℃, and pressure can reach 10MPa, can simulate China in-service, build with the advanced pressurized water reactor nuclear power plant secondary circuit operating mode such as the AP1000 that will build in the future.The working temperature of apparatus of the present invention is 280 ℃, and pressure limit is 0.1～6.5MPa;
(4) mode that apparatus of the present invention heat in adopting is directly to the water heating in primary heater, and firing rate is fast, and temperature control is accurate, heat-transfer pipe thermal load 0-8.2 × 105KJ/m
2h is adjustable continuously; The variation of steam generator heat-transfer pipe primary side hot-fluid can simulate the reduction-shutdown of nuclear power station reactor startup-power ascension-Operation at full power-power time; Experimental section inside is electrical heating elements, realizes the simulation to steam generator heat-transfer pipe thermal load by adjusting electrical heating power.
Accompanying drawing explanation
Fig. 1 is that a kind of nuclear power station steam generator impurity of the present invention concentrates and the gap impurity of the simulation test device the returning experiment flow figure that concentrates;
Fig. 2 be a kind of nuclear power station steam generator impurity of the present invention concentrate with the embodiment mono-gap sample tap of the simulation test device returning and loop in other position concentration impurity ion comparison diagram;
Fig. 3 is that a kind of nuclear power station steam generator impurity of the present invention concentrates and simulates after shutdown chlorine ion concentration in autoclave with the embodiment bis-of the simulation test device returning and scheme over time;
Fig. 4 is that a kind of nuclear power station steam generator impurity of the present invention concentrates and simulates after shutdown chlorine ion concentration in the sampling jar of loop with the embodiment tri-of the simulation test device returning and scheme over time;
Fig. 5 is that a kind of nuclear power station steam generator impurity of the present invention concentrates and simulates after shutdown chlorine ion concentration in the water pitcher of loop with the embodiment tetra-of the simulation test device returning and scheme over time;
Fig. 6 is that a kind of nuclear power station steam generator impurity of the present invention concentrates and simulates after shutdown loop with the embodiment five of the simulation test device returning and return to chlorine ion concentration in water and scheme over time.
Embodiment
Below in conjunction with accompanying drawing, technical characterictic and the advantage with other above-mentioned to the present invention are described in more detail.
Below a kind of nuclear power station steam generator impurity of the present invention is concentrated and described in detail with the process of the simulation test device returning.Employing electrically heated rod in the present invention carrys out direct modeling one loop thermal source, and energy efficiency is high, and the rate of heat addition is fast.Secondary circuit moisturizing enters autoclave (model steam generator secondary side) after being heated to design temperature by primary heater, in adopting, the mode of heating is directly to the water heating in primary heater, firing rate is fast, and temperature control is accurate, accurately adjustable continuously in the temperature range of needs.
Refer to shown in Fig. 1, it concentrates and the gap impurity of the simulation test device the returning experiment flow figure that concentrates for a kind of nuclear power station steam generator impurity of the present invention.The device of this experiment flow comprises a high pressure preheating unit, a circular treatment unit and a voltage-stabilizing protection unit.Described high pressure preheating unit comprises an autoclave 1, a double-tube heat exchanger 2 and a primary heater 3.Described autoclave comprises a cooling water outlet 11 and a cooling water intake 12.Described autoclave is connected with double-tube heat exchanger 2 by a stop valve, and described double-tube heat exchanger 2 is connected with primary heater 3 front ends, and described primary heater 3 rear ends are connected with autoclave 1 by a stop valve.Chilled water becomes high-temperature high pressure water after entering autoclave 1, high-temperature high pressure water in autoclave double-tube heat exchanger 2 outer tubes of flowing through, after water in double-tube heat exchanger 2 inner tubes is heated, send into primary heater 3, the interior circular treatment of autoclave 1 sent into the water after preheating again by primary heater 3, and capacity usage ratio is improved greatly.
Described autoclave 1 is model steam generator heat-transfer pipe secondary side temperature and pressure, experimental section is the border of model steam generator heat-transfer pipe primary side and secondary side, primary side is mainly simulated the thermal load of primary side of steam generator of nuclear power plant by electrical heating elements, secondary side is by temperature and the pressure of autoclave model steam generator secondary side.Primary heater 3 is model steam generator feed temperature.Temperature after the Steam Actuation steam turbine that double-tube heat exchanger 2 produces for model steam generator does work declines, and the water that another act as heating inner sleeve, causes the water temperature that enters primary heater to be unlikely to too low, improves capacity usage ratio.
Described circular treatment unit comprises a refrigeratory 4, a filtrator 5, a voltage stabilizing impact damper 6, a collecting box 7 and a precision plunger pump 8.A described precision plunger pump 8 becomes normal temperature low-pressure water normal temperature high voltage water after precision plunger pump, then pumps in described double-tube heat exchanger 2.Described refrigeratory 4 comprises a cooling water outlet 41 and chilled water water inlet 42.Described refrigeratory 4 is connected with filtrator 5 by a safety valve 101, and described filtrator is connected with described voltage stabilizing impact damper 6 with a stop valve by a reduction valve 104, and described voltage stabilizing impact damper 6 is connected with collecting box 7 by a stop valve.Described collecting box 7 is connected with described precision plunger pump 8.Described filtrator is also connected with collecting box 7 with a stop valve by described reduction valve 104.
Described refrigeratory 4 uses tap water chilled water tank that high-temp liquid is lowered the temperature, and the rear energy decreases of water vapor pushing turbine acting that act as model steam generator generation finally becomes aqueous water process.Described filtrator 5 directly filters out the various granule foreigns in loop, act as the solid impurity in filtration circuit, prevents impurity blocking pipe in loop.The effect of described voltage stabilizing impact damper 6 is mainly the volume of adjusting water in loop.The effect of described collecting box 7 is mainly the water sampling in loop.The border that described precision plunger pump 8 is high-low pressure, act as and normal temperature low-pressure water is become after precision plunger pump to normal temperature high voltage water.
Described voltage-stabilizing protection unit comprises that a gas cylinder 9, a voltage stabilizing impact damper 6 and gas cylinder described in an autoclave 1. are connected with voltage stabilizing impact damper 6 with autoclave 1 by a stop valve respectively, thereby loop is protected.Described autoclave 1 comprises an experimental section, described experimental section is inner simulates a loop steam generator heat-transfer pipe thermal load for electrical heating elements, experimental section is outside is simulation secondary circuit operating mode, therefore between experimental section simulation heat transfer tube wall and tube sheet, there is the temperature difference, the existence of the temperature difference is constantly seethed with excitement liquid bulk in gap, and various impurity constantly concentrates in slit region.Described gas cylinder 9 comprises nitrogen cylinder and helium tank, described nitrogen cylinder act as loop deoxygenation, the experimental section that act as of described helium tank fills the protection of helium high-temperature oxydation and heat conduction.In the middle of heating rod and heat-transfer pipe, be filled with helium, its objective is the heat conduction and the anti-oxidation that increase between heating rod and heat-transfer pipe, high pressure helium gas cylinder is not directly connected with heating rod, but the middle helium surge tank that connects, be in order to keep the pressure of helium in gap steady, increase the stability of heat conduction.
For impurity return course, rear end at described precision plunger pump 8 has increased pressure regulator valve, at the middle safety valve 101 that has been connected of refrigeratory and surge tank, between refrigeratory and filtrator, there is a safety valve, adjust this safety valve and can control the pressure of whole circuit system, reach by the change of circuit system pressure the object that impurity returns.
Below a kind of nuclear power station steam generator impurity of the present invention is concentrated and described in detail with the process of the simulation test device returning.
Described precision plunger pump 8 pushes double-tube heat exchanger inner tube normal-temperature water, and the heat interchanger outer tube of flowing through of the high-temperature high pressure water in described autoclave 1 is sent into primary heater 3 after water in described double-tube heat exchanger 2 inner tubes is heated; After refrigeratory, connect filtrator, in coiled pipe, high-temp liquid becomes normal-temperature water through tap water chilled water tank, is then back to collecting box through safety valve, completes whole loop flow process.
For impurity return course, increase by a stop valve in the rear end of precision plunger pump 8, be connected safety valve at refrigeratory 3 with in the middle of surge tank 2, by speed and the amplitude of pressure regulator valve and safety valve common regulating loop system supercharging and step-down, adjust this safety valve and can control the pressure of whole circuit system, reach by the change of circuit system pressure the object that impurity returns.
Below a kind of nuclear power station steam generator impurity of the present invention is concentrated and described in detail with the embodiment of the simulation test device returning.
Embodiment mono-: the gap impurity experiment of concentrating
Refer to shown in Fig. 2 and table one, it is chlorine ion concentration comparison diagram/table everywhere in loop after concentrating for 28 hours.When precision plunger pump stroke is 20%, flow is 12L/h, and thermal load is 2.68 × 105KJ/m
2h.The temperature of primary heater and autoclave is respectively 240 ℃ and 280 ℃, and it is 9.6 that morpholine regulates pH, and bulk solution chlorine ion concentration is 1mg/L.Concentrate after 28 hours, concentration factor is 1.75 × 10
4doubly.
Concentration impurity ion in the sampling jar of No. 1 position (gap) after 28-1 refers to concentrate 28 hours in horizontal ordinate in Fig. 2,28-2 is concentration impurity ion in autoclave, 28-3 is concentration impurity ion in sampling jar, and 28-4 is concentration impurity ion in water pitcher, and 28-4R is for returning concentration impurity ion in water.After above-mentioned operating mode concentrates for 28 hours, gap sampling jar middle high-pressure still, sampling jar, water pitcher and return impurity chlorine ion concentration in water and be respectively 162mg/L, 1.7mg/L, 1.03mg/L, 1.12mg/L and 1.65mg/L.Calculating thus slit region impurity concentration factor is 1.75 × 10
4doubly.The computing formula of concentration factor is: F=40 (c1-c2)/0.364, F is impurity concentration factor, and 40 are fixed as 40mL for each sample volume, and 0.364 is gap volume 0.364mL, c1 is the concentration impurity ion in the sampling jar of 1# position, and c2 is concentration impurity ion in the autoclave of 2# position.Can simulate concentrate phenomenon and the rule that concentrates of foreign ion under nuclear power station working condition.
Other position concentration impurity ion contrast table in table 1 gap sample tap and loop
Embodiment bis-: gap impurity returns to experiment
The condition of work that described experimental provision impurity returns to the preparation of sample is, pump stroke is 30%, and flow is 19.8L/h, and primary heater temperature is 240 ℃, and autoclave temp is 280 ℃, and experimental section thermal load is 2.49 × 105KJ/m
2h.Regulating pH value with morpholine is 9.6, and the time of concentrating is 24 hours, and concentration factor is 2.67 × 10
4doubly.Concentrating after 24 hours, cutting off experimental section power supply, the desired temperature of primary heater and autoclave is being reduced to 180 ℃ (mock-up reactor shutdowns) simultaneously at once.In Fig. 3-6 or shown in table 2-5,0h is that experimental section stops heating, and after primary heater and autoclave design temperature are 180 ℃, chlorine ion concentration changes.0.5h is quick transformation (4MPa-0.1MPa-4MPa) for the first time, and pressure release is 5 seconds, and boosting is 60 seconds, and water pitcher volume change can be ignored.1h is quick transformation for the second time, and 2h is quick transformation for the third time, and 3h is the 4th quick transformation, and 4h is the 5th quick transformation, and 20h is the 6th quick transformation, and 22h is the 7th time, and 24h is the 8th time, and 26h is the 9th time, and 28h is the tenth time.
Return to technique through 28 hours impurity, it is 98% that impurity returns to efficiency, and the computing formula of returning to efficiency is: the computing formula that impurity returns to efficiency eta is: η=(k1-k2)/k1
In formula, k1 is for returning to concentration impurity ion in the sampling jar of front gap, and k2 is for returning to after technique concentration impurity ion in the sampling jar of gap.
Refer to shown in Fig. 3 and table 2, it is that in autoclave of the present invention, chlorine ion concentration is schemed over time.From Fig. 3 and table 2: chlorine ion concentration fast-descending before this in autoclave, then slowly increases along with the increase of transformation number of times (time).
Table 2 is simulated after shutdown chlorine ion concentration in autoclave and is shown over time
Refer to shown in Fig. 4 and table 3, it is schemed over time/show, the concentration of chlorion slowly increase along with the increase of transformation number of times (time) in sampling jar for intending after shutdown chlorine ion concentration in the sampling jar of loop.
Table 3 is simulated after shutdown chlorine ion concentration in sampling jar and is shown over time
Refer to shown in Fig. 5 and table 4, it is for scheming over time/show for chlorine ion concentration in loop water pitcher after simulation shutdown, and in water pitcher, the concentration of chlorion increases along with the increase of transformation number of times (time).
Table 4 is simulated after shutdown chlorine ion concentration in water pitcher and is shown over time
Refer to shown in Fig. 6 and table 5, its for simulation shutdown after loop return chlorine ion concentration in water and scheme over time/show.
Table 5 is simulated and is returned chlorine ion concentration in water after shutdown and show over time
From Fig. 6 and table 5: the concentration of returning to chlorion in water increases before this fast, then slowly increases along with the increase of transformation number of times (time).
Return in technique at impurity, the concentration of chlorion fast-descending before this in autoclave, then along with the prolongation rising of time of return; And be all progressively to rise along with the prolongation of time of return for the variation of chlorine ion concentration in sampling jar, water pitcher and backwater.Illustrate that the impurity in gap progressively turns back in system along with returning to the prolongation of time in technique.Utilize this contrive equipment, adopt transformation technique can realize returning of gap foreign ion, return to efficiency and can reach 98%.Illustrate that apparatus of the present invention can be for the concentrate research of returning of impurity of nuclear power station steam generator heat-transfer pipe and tube sheet gap.
The foregoing is only preferred embodiment of the present invention, is only illustrative for invention, and nonrestrictive.Those skilled in the art is understood, and in the spirit and scope that limit, can carry out many changes to it in invention claim, revise, and even equivalence, but all will fall within the scope of protection of the present invention.
Claims (10)
1. nuclear power station steam generator impurity concentrates and the simulation test device returning, and it comprises a voltage-stabilizing protection unit, it is characterized in that, it also comprises a high pressure preheating unit and a circular treatment unit;
Described high pressure preheating unit comprises a double-tube heat exchanger, and cooling liquid is carried out thermal pretreatment by the high temperature high pressure liquid that described double-tube heat exchanger utilizes described high pressure preheating unit to produce, then the liquid after described thermal pretreatment is carried out to HIGH PRESSURE TREATMENT;
Described circular treatment unit comprises that a cooling filtering device, an aqueous water pump into device and a voltage stabilizing snubber assembly; Described cooling filtering device is in order to become the various granule foreigns in aqueous water and filtration circuit by the water vapor cooling of high temperature; Described aqueous water pumps into device in order to normal temperature low-pressure liquid water is become to normal temperature high voltage aqueous water, then pumps in described double-tube heat exchanger; Described voltage stabilizing snubber assembly is in order to adjust the volume of aqueous water in loop;
Described voltage-stabilizing protection unit comprises a gas cylinder, and described gas cylinder is connected with circular treatment unit with described high pressure preheating unit by a stop valve respectively.
2. nuclear power station steam generator impurity according to claim 1 concentrates and the simulation test device returning, it is characterized in that,
Described high pressure preheating unit also comprises an autoclave and a primary heater, described autoclave is connected with described double-tube heat exchanger by a stop valve, described double-tube heat exchanger is connected with described primary heater front end, and described primary heater rear end is connected with described autoclave by a stop valve;
The flow through outer tube of described double-tube heat exchanger of high temperature high pressure liquid in described autoclave, will send into primary heater after the water heating in double-tube heat exchanger inner tube, and primary heater is sent the water after preheating into circular treatment in autoclave again; Described double-tube heat exchanger outer tube is connected with described cooling filtering device.
3. nuclear power station steam generator impurity according to claim 2 concentrates and the simulation test device returning, it is characterized in that,
Described cooling filtering device comprises a refrigeratory and a filtrator;
Described refrigeratory is in order to become aqueous water by the water vapor cooling of high temperature, and described filtrator is in order to directly to filter out the various granule foreigns in loop; Between described refrigeratory and described filtrator, have a safety feature, described safety feature is in order to adjust the pressure of controlling whole circuit system.
4. nuclear power station steam generator impurity according to claim 1 concentrates and the simulation test device returning, it is characterized in that,
Described circular treatment unit also comprises a collecting box, for to loop liquid sampling; The water inlet end of described collecting box is connected with the water outlet end of described voltage stabilizing snubber assembly.
5. nuclear power station steam generator impurity according to claim 4 concentrates and the simulation test device returning, it is characterized in that,
Described aqueous water pumps into device and is connected with the water outlet end of collecting box, in order to normal temperature low-pressure water process is become to normal temperature high voltage water, then pumps in described double-tube heat exchanger inner tube.
6. nuclear power station steam generator impurity according to claim 5 concentrates and the simulation test device returning, it is characterized in that,
Described gas cylinder comprises nitrogen cylinder and helium tank, and described nitrogen cylinder is in order to loop deoxygenation, and described helium tank is with thinking that the experimental section in described autoclave fills helium.
7. concentrate and the simulation test device returning according to the nuclear power station steam generator impurity described in above-mentioned any one claim, it is characterized in that, the condition of work that described experimental provision impurity concentrates is for being: precision plunger pump stroke is 20%, and flow is 12L/h, and thermal load is 2.68 × 105KJ/m
2h, the temperature of primary heater and autoclave is respectively 240 ℃ and 280 ℃, and it is 9.6 that morpholine regulates pH, and bulk solution chlorine ion concentration is 1mg/L.
8. nuclear power station steam generator impurity according to claim 7 concentrates and the simulation test device returning, it is characterized in that,
Concentrating in technique of described impurity, the computing formula of concentration factor is:
F=40(c1-c2)/0.364，
In formula, F is impurity concentration factor, and 40 are fixed as 40mL for each sample volume, and 0.364 is gap volume 0.364mL, and c1 is the concentration impurity ion in sampling jar, and c2 is concentration impurity ion in autoclave.
9. concentrate and the simulation test device returning according to the nuclear power station steam generator impurity described in above-mentioned any one claim, it is characterized in that, the condition of work that described experimental provision impurity returns to the preparation of sample is: pump stroke is 30%, flow is 19.8L/h, primary heater temperature is 240 ℃, autoclave temp is 280 ℃, and experimental section thermal load is 2.49 × 105KJ/m2h; Concentrating after 24 hours, cutting off experimental section power supply, the desired temperature of primary heater and autoclave is being reduced to 180 ℃ simultaneously.
10. nuclear power station steam generator impurity according to claim 9 concentrates and the simulation test device returning, it is characterized in that,
Returning in technique of described impurity, the computing formula that impurity returns to efficiency eta is:
η=(k1-k2)/k1
In formula, k1 is for returning to concentration impurity ion in the sampling jar of front gap, and k2 is for returning to after technique concentration impurity ion in the sampling jar of gap.
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| CN106404431A (en) * | 2015-08-10 | 2017-02-15 | 核动力运行研究所 | Steam generator blowdown testing device |
| CN107621334A (en) * | 2016-07-15 | 2018-01-23 | 核工业西南物理研究院 | For hot helium leak test gas heating circulation system and quickly heat cooling means |
| CN112798310A (en) * | 2020-12-30 | 2021-05-14 | 西安交通大学 | Test loop and method for simulating steam generator with or without axial flow preheater |
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| CN112798310A (en) * | 2020-12-30 | 2021-05-14 | 西安交通大学 | Test loop and method for simulating steam generator with or without axial flow preheater |
| CN112798310B (en) * | 2020-12-30 | 2021-12-07 | 西安交通大学 | Test loop and method for simulating steam generator with or without axial flow preheater |
| US20220205630A1 (en) * | 2020-12-30 | 2022-06-30 | Xi'an Jiaotong University | Test Loop for Simulating Steam Generator with or without Axial Economizer and Test Method Thereof |
| US11754281B2 (en) * | 2020-12-30 | 2023-09-12 | Xi'an Jiaotong University | Test loop for simulating steam generator with or without axial economizer and test method thereof |
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