CN109741842B - Nuclear power plant capacity control box deoxygenation testing system and method - Google Patents
Nuclear power plant capacity control box deoxygenation testing system and method Download PDFInfo
- Publication number
- CN109741842B CN109741842B CN201910011687.1A CN201910011687A CN109741842B CN 109741842 B CN109741842 B CN 109741842B CN 201910011687 A CN201910011687 A CN 201910011687A CN 109741842 B CN109741842 B CN 109741842B
- Authority
- CN
- China
- Prior art keywords
- flow
- pressure
- oxygen content
- controlling
- control box
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Images
Classifications
-
- 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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a nuclear power plant volume control box deoxidization test system and a method, wherein the system comprises an upper charging and lower discharging system, a purging system, an oxygen content adjusting system, a temperature control system and a parameter monitoring system, the test system of the invention provides the functions of flow control, temperature adjustment, oxygen content control, nitrogen gas supply, gas discharge and the like of upper charging flow and lower discharging flow, and the test of 'intermittent purging' and 'pressure-building exhaust' can be realized based on the functions, and the invention also designs corresponding test methods respectively according to different working conditions, and obtains the influence rule of the liquid level, the waiting time and the purging time of the volume control box on the 'intermittent purging' deoxidization effect through the test; and obtaining the rule of influence of the standing time on the pressure-building exhaust oxygen removal effect; and through comparison of test data of the two methods, the difference of the 'intermittent blowing' method and the 'pressure-holding exhaust' method in the deoxidization effect can be obtained, and better data support is provided for optimization and adjustment of the actual unit deoxidization strategy.
Description
Technical Field
The invention relates to the field of nuclear power, in particular to a nuclear power plant capacity control box deoxygenation testing system and method.
Background
The chemical and volume control system is used as one of nuclear auxiliary systems of the pressurized water reactor nuclear power unit and plays an important role in operation; wherein the volume control action compensates for the coolant loop water body caused in the cold-state to hot-state zero-power starting process or the hot-state zero-power to cold shutdown process of the nuclear power plantThe product changes. Fig. 1 is a schematic control diagram of a primary containment system, in which a containment system including a containment tank and the like is connected to a coolant circuit during normal power generation in order to maintain a constant water level in the coolant circuit. The pipes and equipment in the coolant loop are made of stainless steel and the dissolved oxygen in the water can cause corrosion to the pipes and equipment. The mechanism of oxygen corrosion is as follows: anode: fe → Fe2 ++2e-(ii) a Cathode: o is2+H2O+4e-→40H-Generation of Fe2 +Will be further oxidized and the corrosion product finally produced is Fe3O4And the increase of the concentration of the dissolved oxygen in the water accelerates the corrosion rate of the equipment, causing the damage of the equipment.
Thus, nuclear power plants have strict control requirements on the amount of oxygen in the coolant. When the unit is started, after the gas quantity of the closed primary circuit meets the requirement, the final deoxygenation of the primary circuit is carried out by using the volume control system. In a volume control system, there are two oxygen balances: first, the equilibrium of dissolved oxygen in the water in the coolant loop with oxygen in the gas in the coolant loop; the second is the balance between the dissolved oxygen in the liquid phase water and the oxygen in the gas phase in the volume control box. Because a dynamic equilibrium process exists between the volume control box and the coolant loop, namely water in the volume control box flows into the coolant loop, and water in the coolant loop also flows into the volume control box, in order to reduce the content of dissolved oxygen in the water in the coolant loop, the content of dissolved oxygen in the water in the volume control box can be reduced. Common oxygen removal methods are: physical oxygen removal and chemical oxygen removal, wherein the basic principle of physical oxygen removal is as follows:
1) dalton partial pressure law: the total pressure of the mixed gas is equal to the sum of partial pressures of the gases, i.e. the total pressure P of the mixed gas on the water surface in the control box is equal to the total pressure N of the gas in the dissolved water2、O2、CO2Etc.) partial pressure
And (3) the sum:
2) henry's law: the solubility of a gas in water is proportional to the partial pressure of the gas above the water surface. I.e. the amount b of gas dissolved in a unit volume of water and the partial pressure P of the gas on the water surfacebIn direct proportion, the expression is as follows:
in the formula: p is the total pressure of the mixed gas, KbIs the weight solubility coefficient of the gas, which is related to the gas species, the partial pressure of the gas at the water surface and the temperature of the water.
3) Equation of mass transfer
Sufficient power (Δ P) is required for the gas to separate out of the water surface, and the mass transfer equation is as follows:
G＝Km·A·ΔP
in the formula: g is the amount of the separation gas; kmIs the mass transfer coefficient; a is the mass transfer area; Δ P is the imbalance pressure difference, i.e., the difference between the equilibrium pressure and the actual partial pressure.
Combining the above formulas, the following conclusions can be drawn: general gas (O) at constant pressure2、CO2Air, etc.) is in direct proportion to the partial pressure of the gas on the liquid surface, and the dissolved amount of the gas tends to zero when the partial pressure of the gas is zero; according to a mass transfer equation, enough unbalanced pressure difference delta P exists, more dissolved gas is contained in water at the initial stage of deoxygenation, delta P is larger, the driving force for overcoming the surface tension of water and separating out the water in a small bubble mode is larger, 80% -90% of gas in the water can be removed, and the oxygen content in the water can be reduced to 0.05-0.1 mg/1 correspondingly. In the later stage of deoxidization, only a small amount of residual gas is dissolved in water, the delta P is small, the gas is difficult to overcome the surface tension segregation of water, and the gas is separated from the water by enlarging the contact surface of the steam and the water (forming a water film with small surface tension) or by the diffusion action of water turbulence.
One method in which chemical oxygen removal is relatively common is to add hydrazine to the coolant water by reaction of the hydrazine with oxygen (N)2H4+O2→N2+2H2O) to remove dissolved oxygen from the water as much as possible. In the prior art, the amount of hydrazine added into a coolant loop is generally determined by empirical values, so that the added amount of hydrazine is easily larger or smaller, and when the usage amount of hydrazine is smaller, dissolved oxygen in water cannot be completely removed; when the usage amount of hydrazine is too large, the extra hydrazine consumes the exchange capacity of the resin of the desalting bed to make the resin ineffective.
The method adopted by the nuclear power plant at present is to carry out physical deoxygenation, and then use hydrazine to carry out chemical deoxygenation after the physical deoxygenation is qualified. The physical oxygen removal method comprises two methods:
1) pressure-building exhaust method: artificially raising the liquid level of the volume control box to a certain height, and manually opening an exhaust valve to exhaust. And carrying out nitrogen purging on the volume control box by a water level lifting method. Firstly, lifting the water level of the control box to a 90% liquid level, and then manually opening an exhaust valve to exhaust the control box; after the air exhaust is finished, the liquid level is reduced to 50%, after the air exhaust is carried out for 2 hours, the gas covering layer is sampled to measure the oxygen content, and the operation is repeated until the oxygen content of the volume control box is qualified.
2) And an intermittent purging exhaust method: continuously purging inert gas N into the volume control box2And is exhausted at intervals. Namely, the exhaust valve of the volume control box is opened for 5 minutes every hour, and nitrogen is used for continuous purging until the oxygen content meets the requirement.
The actual operation of using the capacity control box to carry out final deoxidization on a primary circuit in the nuclear power plant at present has the following problems: in the related method for testing the deoxidization performance of the existing control-box-free deoxidization performance, the deoxidization operation of the control box is carried out according to empirical parameters, so that the problem that the control box cannot be qualified by once purging exists, and the overhaul time is occupied; when the residual air amount in the primary circuit before purging changes, the oxygen removal strategy cannot be flexibly adjusted according to the actual situation.
Disclosure of Invention
The invention aims to solve the technical problem of providing a nuclear power plant capacity control box deoxygenation testing system and method aiming at the defects in the prior art.
The technical scheme adopted by the invention for solving the technical problems is as follows:
an embodiment of the present invention provides a nuclear power plant capacity control box deoxidization testing system, including:
the upper filling and lower discharging system comprises a buffer container, a lower discharging pipeline for guiding liquid in the buffer container into the containing and controlling box, an upper filling pipeline for guiding the liquid in the containing and controlling box back to the buffer container, and an upper filling and lower discharging control unit, wherein the upper filling and lower discharging control unit is used for controlling the flow and pressure of lower discharging flow in the lower discharging pipeline and upper filling flow in the upper filling pipeline;
the purging system is connected with the containing and controlling box and can be used for injecting nitrogen into the containing and controlling box and discharging gas in the containing and controlling box;
the oxygen content adjusting system is connected with the lower bleed pipeline and can be used for injecting oxygen into the lower bleed to adjust the oxygen content in the lower bleed;
the temperature control system is connected with the buffer container and is used for introducing heated steam into the liquid in the buffer container so as to adjust the temperature of the liquid;
and the parameter monitoring system is used for monitoring the flow, pressure and oxygen content of the lower discharge flow and the upper charging flow, and monitoring the pressure, liquid level, gas oxygen content and liquid oxygen content in the containing and controlling box.
Optionally, the upper charging and discharging control unit includes:
set up on filling the pipeline: the device comprises an upper charging pump, an upper charging isolation valve positioned on the upstream of the upper charging pump, and an upper charging flow regulating valve positioned on the downstream of the upper charging pump;
set up on the bleeder line: the lower bleed pump, a lower bleed isolation valve positioned at the upstream of the lower bleed pump and a lower bleed pressure reducing valve positioned at the downstream of the lower bleed pump, wherein the downstream of the lower bleed pressure reducing valve is connected with the oxygen content regulating system;
the buffer container comprises a bypass pipeline and a lower leakage flow regulating valve arranged on the bypass pipeline, wherein the bypass pipeline is connected between the downstream of the lower leakage flow reducing valve and the buffer container.
Optionally, the purging system comprises a nitrogen bottle filled with nitrogen, a nitrogen purging pipeline connected with the nitrogen bottle and the containing and controlling box, a pressure stabilizing valve arranged on the nitrogen purging pipeline, an exhaust pipeline connected with the top of the containing and controlling box, and an exhaust valve arranged on the exhaust pipeline.
Optionally, the oxygen content adjusting system includes: the air compressor is connected with a lower discharge pipeline through the aeration pipeline and is also connected with the top of the containing and controlling box through the containing and controlling box air injection pipeline.
Optionally, the parameter monitoring system includes various sensors arranged in the upper charging and discharging system, the nitrogen purging system, the oxygen regulating system and the volume control box for collecting oxygen content, liquid level, flow, pressure and temperature data.
Optionally, the test system further includes:
and the liquid injection system comprises a water replenishing pipeline connected with the bottom of the volume control box, a deoxidizing device arranged on the water replenishing pipeline, a water replenishing pump positioned on the downstream of the deoxidizing device, and a water replenishing valve positioned on the downstream of the water replenishing pump.
In another aspect, an embodiment of the present invention provides a nuclear power plant capacity control box deoxygenation testing method, which is implemented based on the foregoing system, and includes: executing a plurality of test experiments based on a plurality of groups of values of the test parameters, wherein each test experiment is executed by taking one group of values of the test parameters; wherein, the test parameter includes test liquid level, single latency and single exhaust time, wherein, the test experiment includes:
the preparation method comprises the following steps: injecting desalted water with specified oxygen content into the control box, and maintaining the temperature of liquid in the control box to be constant through a steam heating system;
a first testing step: adjusting the liquid level of a containing and controlling box to the testing liquid level, controlling the flow of lower discharge and upper charge to be zero through the upper charge and lower discharge control unit, and maintaining the pressure in the containing and controlling box at a first preset pressure through the purging system;
and a second testing step: and performing intermittent purging until the parameter monitoring system monitors that the oxygen content of the gas in the volume control box is stable, wherein the intermittent purging comprises the following steps: controlling the gas in the containing and controlling box to be exhausted for one time according to the single exhausting time by the purging system every other single waiting time;
and a third testing step: determining a time to perform the intermittent purge, and determining a change in an oxygen level of the liquid in the containment tank before and after performing the intermittent purge based on the parameter monitoring system.
In another aspect, an embodiment of the present invention provides a nuclear power plant capacity control box deoxygenation testing method, which is implemented based on the foregoing system, and includes:
the preparation method comprises the following steps: injecting the deaerated water into the control box, and maintaining the temperature of the liquid in the control box to be constant through a steam heating system;
a first testing step: maintaining the flow stability of the upper charging flow and the flow stability and pressure stability of the lower discharging flow through the upper charging and lower discharging control unit, and maintaining the pressure in the volume control box at a second preset pressure through the purging system;
and a second testing step: adjusting the oxygen content in the lower discharge flow to a preset stable value through an oxygen content adjusting system;
and a third testing step: controlling the flow rates of upper filling and lower discharging through the upper filling and lower discharging control unit so as to enable the liquid level of the containing and controlling box to be raised to a first liquid level, discharging gas in the containing and controlling box through the purging system, and maintaining the pressure in the containing and controlling box at a third preset pressure;
and a fourth testing step: controlling the flow rates of the upper filling flow and the lower discharging flow through the upper filling and lower discharging control unit so as to reduce the liquid level of the containing and controlling tank and maintain the liquid level at a second liquid level;
a fifth testing step: and standing, wherein the oxygen content in the lower discharge flow is adjusted to a preset stable value through an oxygen content adjusting system in the standing process, and the change conditions of the oxygen content of the gas and the oxygen content of the liquid are recorded in real time based on the parameter monitoring system in the standing process.
In another aspect, an embodiment of the present invention provides a nuclear power plant capacity control box deoxygenation testing method, which is implemented based on the foregoing system, and includes: executing a plurality of test experiments based on a plurality of groups of values of the test parameters, wherein each test experiment is executed by taking one group of values of the test parameters; wherein, the test parameter includes test liquid level, single latency and single exhaust time, wherein, the test experiment includes:
the preparation method comprises the following steps: injecting desalted water with specified oxygen content into the control box, and maintaining the temperature of liquid in the control box to be constant through a steam heating system;
a first testing step: adjusting the liquid level of a containing and controlling box to the testing liquid level, maintaining the stable flow of the upper charging flow and the stable flow and pressure of the lower discharging flow through the upper charging and lower discharging control unit, discharging gas in the containing and controlling box through the purging system, and maintaining the pressure in the containing and controlling box at a fourth preset pressure;
and a second testing step: and performing intermittent purging until the parameter monitoring system monitors that the oxygen content of the gas in the volume control box is stable, wherein the intermittent purging comprises the following steps: controlling the gas in the containing and controlling box to be exhausted for one time according to the single exhausting time by the purging system every other single waiting time;
and a third testing step: determining a time to perform the intermittent purge, and determining a change in an oxygen level of the liquid in the containment tank before and after performing the intermittent purge based on the parameter monitoring system.
In another aspect, an embodiment of the present invention provides a nuclear power plant capacity control box deoxygenation testing method, which is implemented based on the foregoing system, and includes:
the preparation method comprises the following steps: injecting the deaerated water into the control box, and maintaining the temperature of the liquid in the control box to be constant through a steam heating system;
a first testing step: maintaining the flow stability of the upper charging flow and the flow stability and pressure stability of the lower discharging flow through the upper charging and lower discharging control unit, and maintaining the pressure in the volume control box at a fifth preset pressure through the purging system;
and a second testing step: controlling the flow rates of upper flow filling and lower flow discharging through the upper flow filling and lower flow discharging control unit so that the liquid level of the containing and controlling box is raised to a first liquid level, discharging gas in the containing and controlling box through the purging system, and maintaining the pressure in the containing and controlling box at a sixth preset pressure;
and a third testing step: controlling the flow rates of the upper filling flow and the lower discharging flow through the upper filling and lower discharging control unit so as to reduce the liquid level of the containing and controlling tank and maintain the liquid level at a second liquid level;
and a fourth testing step: and standing, wherein the oxygen content in the lower discharge flow is adjusted to a preset stable value through an oxygen content adjusting system in the standing process, and the change conditions of the oxygen content of the gas and the oxygen content of the liquid are recorded in real time based on the parameter monitoring system in the standing process.
The nuclear power plant capacity control box deoxidization testing system and method have the following beneficial effects: the testing system provided by the invention provides functions of flow control of upper charging flow and lower discharging flow, temperature regulation of lower discharging flow, oxygen content control of lower discharging flow, nitrogen supply, gas discharge and the like, and based on the functions, tests of 'intermittent blowing' and 'pressure-building exhaust' can be realized, and corresponding testing methods are respectively designed under different working conditions of 'intermittent blowing' and 'pressure-building exhaust' to test the oxygen removal effect of 'intermittent blowing' and 'pressure-building exhaust' on the volume control box, and the influence rule of key factors such as liquid level of the volume control box, single waiting time and single blowing time on the oxygen removal effect of 'intermittent blowing' is obtained through the tests; and obtaining the rule of influence of the standing time on the pressure-building exhaust oxygen removal effect through testing; and through comparison of test data of the two methods, the difference of the 'intermittent blowing' method and the 'pressure-holding exhaust' method in the deoxidization effect can be obtained, and a better data support is provided for adjustment of an actual unit deoxidization strategy.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to the provided drawings without creative efforts:
FIG. 1 is a schematic control diagram of a looping system;
FIG. 2 is a schematic structural diagram of a nuclear power plant capacity control box deoxygenation testing system.
Detailed Description
To facilitate an understanding of the invention, the invention will now be described more fully with reference to the accompanying drawings. Exemplary embodiments of the invention are shown in the drawings. This invention may, however, be embodied in many different forms and should not be construed as limited to the embodiments set forth herein. Rather, these embodiments are provided so that this disclosure will be thorough and complete. It should be understood that the embodiments and specific features in the embodiments of the present invention are described in detail in the present application, but not limited to the present application, and the features in the embodiments and specific features in the embodiments of the present invention may be combined with each other without conflict.
It is noted that the terms "connected" or "connected," as used herein, include not only the direct connection of two entities, but also the indirect connection through other entities with beneficial and improved effects.
Unless defined otherwise, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this invention belongs. The terminology used in the description of the invention herein is for the purpose of describing particular embodiments only and is not intended to be limiting of the invention.
The terms including ordinal numbers such as "first", "second", and the like used in the present specification may be used to describe various components, but the components are not limited by the terms. These terms are used only for the purpose of distinguishing one constituent element from other constituent elements. For example, a first component may be named a second component, and similarly, a second component may also be named a first component, without departing from the scope of the present invention.
Referring to fig. 2, fig. 2 is a schematic structural diagram of the oxygen removal testing system for the nuclear power plant capacity control box, wherein solid lines represent liquid pipelines and dashed lines represent gas pipelines. The nuclear power plant capacity control box deoxidization test system of this embodiment mainly includes below: the device comprises an upper charging and discharging system, a purging system, an oxygen content adjusting system, a temperature control system and a parameter monitoring system.
The upper filling and lower discharging system comprises a buffer container, a lower discharging pipeline for guiding liquid in the buffer container into the containing and controlling box, an upper filling pipeline for guiding the liquid in the containing and controlling box back to the buffer container, and an upper filling and lower discharging control unit, wherein the upper filling and lower discharging control unit is used for controlling the flow and pressure of lower discharging flow in the lower discharging pipeline and upper filling flow in the upper filling pipeline, and the upper filling and lower discharging control unit comprises:
the purging system is connected with the containing and controlling box and can be used for injecting nitrogen into the containing and controlling box and discharging gas in the containing and controlling box;
the oxygen content adjusting system is connected with the lower bleed pipeline and can be used for injecting oxygen into the lower bleed to adjust the oxygen content in the lower bleed;
the temperature control system is connected with the buffer container and is used for introducing heated steam into the liquid in the buffer container so as to adjust the temperature of the liquid;
and the parameter monitoring system is used for monitoring the flow, pressure and oxygen content of the lower discharge flow and the upper charging flow, and monitoring the pressure, liquid level, gas oxygen content and liquid oxygen content in the containing and controlling box.
In the invention, a containing and controlling box is used as a tested part and is consistent with actual equipment, specifically, the containing and controlling box is a vertical pressure-bearing container, the top and the bottom of the containing and controlling box are of a spherical welding end enclosure structure, in the embodiment, a plurality of interfaces of an upper end enclosure are respectively used for connecting a lower discharge pipeline and related pipelines in a purging system, nozzles are arranged inside the interfaces for connecting the lower discharge pipeline, and when a nuclear power unit operates, coolant of a primary circuit enters the containing and controlling box through the lower discharge pipeline and is atomized and sprayed when passing through the nozzles at the top in the containing and controlling box. And the interface of the lower end socket of the containing and controlling box is used for connecting an upper charging pipeline, and the coolant in the containing and controlling box is re-injected into a loop through an upper charging pipeline.
The above five system configurations will be described in detail below.
In this embodiment, fill the system of letting out down and utilize buffer container to realize the buffering, buffer container adopts the mode that floats a structure or film cover to seal to isolated outside air is to the influence that contains oxygen volume in the buffer container. The buffer container, the lower discharge pipeline, the volume control box, the upper charging pipeline and the like form a closed cycle, a water inlet pipeline provided with a water inlet valve V5 is connected to the position, close to the top, of the side wall of the buffer container, a water discharge pipeline provided with a water discharge valve V4 is connected to the position, close to the top, of the side wall of the buffer container, corresponding liquid can be injected into the buffer container by controlling the water inlet valve V5 and the water discharge valve V4, and in the embodiment, the buffer container is specifically a buffer water tank.
In one possible embodiment, the upper charging and lower discharging control unit comprises the following three parts:
1) set up on filling the pipeline: an upper charge pump PO2, an upper charge isolation valve 033VP upstream of the upper charge pump PO2, an upper charge flow regulating valve 046VP downstream of the upper charge pump PO 2. Preferably, a bypass line is connected between the inlet and the outlet of the charge pump PO2, and a small flow regulating valve V3 is provided in the bypass line.
2) Set up on the bleeder line: a letdown pump PO1, a letdown isolation valve V1 upstream of the letdown pump PO1, and a letdown relief valve 013VP downstream of the letdown pump PO 1.
Preferably, a nozzle structure is arranged in a pipeline downstream of the lower bleed flow reducing valve 013VP, and gas exhausted by the oxygen content adjusting system is mixed into the lower bleed flow through the nozzle structure, so that the oxygen content of the lower bleed flow is controlled.
3) The bypass line is connected between the downstream of the lower bleed pressure reducing valve 013VP (specifically, between the position connected to the oxygen content adjusting system and the outlet of the lower bleed pressure reducing valve 013 VP) and the buffer container, and is used for shunting the flow at the outlet of the lower bleed pump PO 1.
Preferably, still be provided with the drainage bypass on the let-down pipeline to use the three-way valve reposition of redundant personnel to let-down flow in the simulation actual process, specifically, the system still includes: the drain valve 030VP1, the drain line and set up the drain valve 030VP2 on the drain line, the drain valve 030VP1 is located and inserts between oxygen content governing system position and the entry of holding the case on the bleeder line, the drain line connect in the low reaches of bleeder pump PO1, specifically insert between oxygen content governing system position and drain valve 030VP 1. In this embodiment, a drain line is also connected to the side wall of the control box near the bottom, and a drain valve V6 is provided in the drain line and can be used for draining water.
With continued reference to FIG. 2, in one possible embodiment, the purge system includes a nitrogen cylinder containing nitrogen, a nitrogen purge line connecting the nitrogen cylinder and the containment tank, a pressure maintenance valve 024VZ disposed on the nitrogen purge line, a vent line connecting the top of the containment tank, a vent valve 286VY disposed on the vent line. Specifically, a nitrogen purging pipeline and an exhaust pipeline are respectively connected with two interfaces at the top of the volume control box, a pressure stabilizing valve 024VZ is used for keeping the nitrogen pressure constant, and an exhaust valve 286VY is used for regulating the nitrogen flow.
With continued reference to fig. 2, in one possible embodiment, the oxygen content regulating system comprises: the aeration control device comprises an air compressor, an aeration pipeline, an aeration flow regulating valve V7 arranged on the aeration pipeline, a volume control box air injection pipeline and a volume control box air injection valve V8 arranged on the volume control box air injection pipeline, wherein the air compressor is connected with the downstream position of a pressure reducing valve 013VP of a lower discharge pipeline through the aeration pipeline on one hand to carry out aeration control on the lower discharge so as to regulate the oxygen content in the lower discharge. On the other hand, the air compressor is also indirectly connected with the top of the volume control box through the air injection pipeline of the volume control box, so that the air pressure of the upper air space of the volume control box is conveniently controlled, and the state that the upper air space of the volume control box is filled with high-pressure air before nitrogen purging in the actual operation process is simulated. Specifically, the volume control box air injection line was connected to the nitrogen purge line at a location downstream of the pressure maintenance valve 024 VZ.
With continued reference to fig. 2, in one possible embodiment, the temperature control system in this embodiment uses steam heating to heat the water throughout the test system to substantially match the actual process temperature and maintain the temperature at 46 ℃. The water heating device comprises an electric heating boiler and a heating pipeline connected with the side wall of a buffer container, wherein water in the heating pipeline is heated by the electric heating boiler and then discharged into the buffer container, and a nozzle is arranged in the buffer container at a connector of the buffer container connected with the heating pipeline.
Preferably, the present embodiment further includes a liquid injection system, and the liquid injection system includes a water replenishing line connected to the bottom of the volume control box, a deaerating device disposed on the water replenishing line, a water replenishing pump PO3 located downstream of the deaerating device, an isolation valve V9 located between the deaerating device and the water replenishing pump PO3, and a water replenishing valve REA018VB located downstream of the water replenishing pump PO 3. In this embodiment, the water replenishing pipeline is connected to the volume control box through the upper water replenishing pipeline, specifically, the water replenishing pipeline is connected to a position of the water replenishing pipeline close to the volume control box, so that the water replenishing pipeline is arranged on the upper water replenishing pipeline to simulate manual water replenishing in an actual process.
With continued reference to FIG. 2, in one possible embodiment, the parameter monitoring system includes various sensors disposed in the upper fill and lower vent system, the nitrogen purge system, the oxygen regulation system, and the containment tank that collect oxygen level, liquid level, flow, pressure, temperature data. For example, in fig. 2, MP denotes a pressure measurement sensor, MT denotes a temperature measurement sensor, MD denotes a flow measurement sensor, MG denotes a dissolved oxygen amount measurement sensor, and 012MN denotes a liquid level measurement sensor. As shown in fig. 2, test points are distributed on an upper charging pipeline, a lower discharging pipeline, a nitrogen purging pipeline, an exhaust pipeline, an aeration pipeline, a heating pipeline, a water replenishing pipeline and a volume control box, each test point is provided with one or more sensors, and key test points are as follows:
arranging various sensors at a lower leakage flow inlet of the volume control box to measure the temperature, pressure, flow and oxygen content of lower leakage flow in real time;
a gas sampling pipeline is arranged on the box body of the volume control box and is used for continuously measuring the gas oxygen content of the gas space of the volume control box;
and a liquid level measuring sensor is arranged on the tank body of the containing and controlling tank and is used for measuring the liquid level of the containing and controlling tank.
And at the outlet of the volume control box, a plurality of sensors are arranged to measure the temperature, pressure, flow and oxygen content of the upper charging flow in real time.
It can be understood that the control of the temperature, flow rate, pressure and liquid level in the present invention can be implemented by performing feedback control on the corresponding control device (such as a valve, an electrically heated boiler, etc.) according to the data monitored by the corresponding sensor. For example, to control the flow of the lower bleed flow to be stable at a certain set flow value, the feedback control may be performed on the lower bleed flow regulating valve according to the flow data monitored by the flow sensor on the lower bleed flow line: if the monitored flow data indicate that the flow is larger than the set flow value, the lower leakage flow regulating valve is closed, otherwise, the lower leakage flow regulating valve is opened. The other temperature, pressure and liquid level control are the same, and the description is omitted here.
Therefore, the system of the embodiment can realize various functions of controlling the upper filling and lower discharging flow, manually supplementing water, controlling the lower discharging water temperature, controlling the lower discharging oxygen content, supplementing nitrogen, discharging gas and the like of the volume control box. On the basis of the functions, the test system can develop a plurality of test contents, and the test contents mainly developed according to different test working conditions are shown in the following table 1:
table 1 test content table
It is understood that the above test contents are executed independently, the first and second test contents may provide theoretically feasible test data to provide reference for the actual unit oxygen removal strategy, the third and fourth test contents may provide practically feasible test data to provide reference for the actual unit oxygen removal strategy, and the third and fourth test contents may preferably be further tested on the basis of the data provided by the first and second test contents. Corresponding method embodiments are provided below for the above various test contents.
Corresponding to the test content, one method embodiment of the present invention provides a nuclear power plant capacity control box oxygen removal test method, which is implemented based on the foregoing system embodiment.
The method of the embodiment comprises the following steps: multiple test experiments are executed based on multiple groups of values of test parameters, each test experiment is executed by taking one group of values of the test parameters, and the test parameters comprise: test level L, single wait time T, and single vent time T. That is, the present embodiment provides L, T, t with n (n ≧ 2) values: [ L1, T1, T1], [ L2, T2, T2], [ L3, T3, T3] … [ Ln, Tn ], a test experiment is performed for each set of values, and the test experiment is described in detail below by taking a set of values [ Li, Ti ] as an example, and comprises:
the preparation method comprises the following steps: injecting W with specified oxygen content into the control box1And the temperature of the liquid in the containment tank is maintained constant by the steam heating system. In particular, the injection of demineralized water may be from a buffer vessel, preferably from a water supply line after the oxygen removal device has been turned off.
A first testing step: and adjusting the liquid level of the containing and controlling box to the testing liquid level Li, controlling the flow of the lower discharge flow and the upper charge flow to be zero through the upper charge and lower discharge control unit, and maintaining the pressure in the containing and controlling box at a first preset pressure through the purging system.
Specifically, the flow of the lower bleed and upper fill flows is controlled to zero by keeping the upper fill and lower bleed pumps off while the upper fill isolation valve 033VP and the lower bleed isolation valve V1 are closed. The pressure in the control tank is maintained at the first preset pressure through a pressure stabilizing valve 024VZ on the nitrogen purge line.
It will also be appreciated that other line related equipment not mentioned, such as the air compressor associated with the aeration line, the regulator valve V7, etc., are in a closed state, as not specifically illustrated, and that other drain lines, make-up lines, etc., are in a closed state.
And a second testing step: and performing intermittent purging until the parameter monitoring system monitors that the oxygen content of the gas in the volume control box is stable, wherein the intermittent purging comprises the following steps: controlling the gas in the containing and controlling box to be exhausted for one time according to the single exhausting time Ti through the purging system every other single waiting time Ti, namely opening the exhaust valve 286VY for one time every other single waiting time Ti, wherein the time for opening the exhaust valve 286VY for one time is Ti.
It should be noted that, during the purging process, the oxygen contents of the lower discharge, the upper fill, the liquid in the control box, and the gas in the control box of the whole cycle may change, and finally, after the intermittent purging is completed, a dynamic balance may be achieved, and when the balance is achieved, the oxygen contents of the liquid in the buffer container, the lower discharge, the upper fill, the liquid in the control box, and the gas in the control box may all reach a stable value, and at this time, the oxygen contents in the liquid in the cycle are the same.
And a third testing step: determining a time T to perform an intermittent purgeoiAnd determining a change in the oxygen content of the liquid in the containment tank before and after performing the intermittent purge based on the parameter monitoring system.
Specifically, before the intermittent purge is performed, the oxygen content of the liquid in the control box, i.e., W mentioned in the above preparation step1As can be seen from the above, the final intermittent purging can reach a dynamic balance, so that the oxygen content W of the liquid in the volume control box can be monitored by the dissolved oxygen measuring sensor2iThe change of the oxygen content of the liquid in the volume control tank before and after the intermittent purging is performed is delta Wi＝W1-W2i。
That is, the present embodiment can acquire the time T at which the intermittent purge is performedoiAnd the time content control boxThe change of the oxygen content of the liquid in the tank is delta WiThe two data can indicate the oxygen removal effect of the intermittent purging because the result data T is obtained by different batches of test experimentsoi、ΔWiDifferent from, so based on the calculation formula
Calculating to obtain the variation X of the oxygen content of the liquid in the time-unit control box in each test experimentiAs an index for determining the oxygen removal efficiency. The X's from all batches of test experiments were then comparediAnd determining a test experiment with the best oxygen removal effect, wherein the value of the test parameter based on the test experiment can be regarded as an optimal value.
Corresponding to the second test content, another method embodiment of the present invention provides a nuclear power plant capacity control box oxygen removal test method, which is implemented based on the foregoing system embodiment, and the method of this embodiment includes the following steps:
the preparation method comprises the following steps: and injecting the water after the deoxidization into the containing and controlling box, and maintaining the temperature of the liquid in the containing and controlling box to be constant through a steam heating system. In this embodiment, it is preferable that the deaerating means is turned on to inject deaerated water into the volume control box from the water supply line.
A first testing step: maintaining the flow stability of the upper charging flow and the flow stability and pressure stability of the lower discharging flow through the upper charging and lower discharging control unit, and maintaining the pressure in the volume control box at a second preset pressure through the purging system;
specifically, on the one hand, the charge-up pump is activated and the valve 033VP is opened, and the valve 046VP is adjusted to maintain the flow rate of the charge-up stream steady, on the other hand, the discharge pump is activated and the valves V1, V2, 013VP, 030VP1 are opened, and the valves V2 and 013VP maintain the flow rate and pressure of the discharge stream steady; and adjusting a pressure stabilizing valve 024VZ on the nitrogen purging pipeline to maintain the pressure in the volume control tank at a second preset pressure.
And a second testing step: adjusting the oxygen content in the lower discharge flow to a preset stable value W through an oxygen content adjusting system1；
Specifically, the air compressor is started, the valve V7 is adjusted, the oxygen content in the lower discharge flow is monitored according to the dissolved oxygen content measuring sensor at the inlet of the volume control box, and finally the oxygen content in the lower discharge flow is stabilized at a preset stable value W1. Similar to the previous embodiment, this embodiment will finally reach a dynamic equilibrium, when the equilibrium is reached, the oxygen contents of the liquid inside, the lower discharge, the upper charge, the liquid inside the control box and the gas inside the control box will all reach a stable value, and the oxygen contents in the liquid in the circulation at this time are all the same and are all W1We can record the oxygen content of the gas in the upper gas space in the control box at this time, which is assumed to be W1a。
And a third testing step: the flow rates of the upper filling flow and the lower discharging flow are controlled through the upper filling and lower discharging control unit so that the liquid level of the containing and controlling box is raised to a first liquid level, the gas in the containing and controlling box is discharged through the purging system, and the pressure in the containing and controlling box is maintained at a third preset pressure.
Specifically, the first liquid level is generally 90% of water level, the flow rate of the upper filling flow can be adjusted by the adjusting valve 046VP, the flow rate of the lower discharging flow can be adjusted by the adjusting valve V2, and we can control the upper filling flow rate to be smaller than the lower discharging flow rate by this method, so as to gradually raise the water level of the volume control box to 90% of water level, then open the exhaust valve 286VY, reduce the pressure in the volume control box to a third preset pressure, and close the exhaust valve 286 VY.
And a fourth testing step: and the flow rates of the upper filling flow and the lower discharging flow are controlled by the upper filling and lower discharging control unit so that the liquid level of the containing and controlling box is reduced and maintained at a second liquid level.
Specifically, the second liquid level is generally 50% water level, and similarly, the upper filling flow rate can be controlled to be larger than the lower discharging flow rate by adjusting valves 046VP and V2, and the water level of the volume control tank is gradually reduced to 50% water level.
A fifth testing step: standing, and adjusting the oxygen content in the lower discharge flow to a preset stable value W through an oxygen content adjusting system in the standing process1The adjusting process can refer to the explanation of the second testing step; and the gas content is recorded in real time based on the parameter monitoring system in the standing processOxygen content and change in the oxygen content of the liquid.
Assuming that the oxygen content of the obtained liquid is recorded as Tsi, W during the whole standing process2i]The oxygen content of the gas is [ Tsi, W2ai]I is less than or equal to N, N represents the recording times of the whole standing process, Tsi represents the standing time during the ith recording, W2iDenotes the i-th recorded oxygen content of the liquid, W2aiThe change of the liquid oxygen content corresponding to different standing time Tsi is obtained as delta W by representing the gas oxygen content recorded at the ith timei＝W1-W2iThus, the oxygen removal efficiency of the oxygen content of the liquid corresponding to different standing time Tsi can be calculated as
Similarly, the oxygen content of the gas has the oxygen removal efficiency of
Then comparing X corresponding to all standing time TsiiOr XaiAnd then the standing time with the optimal oxygen removing effect can be determined.
It is understood that the above example is to select the optimal standing time by processing discrete data, and actually, X can also be obtained by curve fittingaiAnd (4) performing a function relation with the Tsi, and then finding the standing time corresponding to the maximum value of the function.
The above-described discrete data analysis is divided into individual transmissions,
corresponding to the third test content, another method embodiment of the present invention provides a nuclear power plant capacity control box oxygen removal test method, which is implemented based on the foregoing system embodiment, and the method of this embodiment includes: multiple test experiments are executed based on multiple groups of values of test parameters, each test experiment is executed by taking one group of values of the test parameters, and the test parameters comprise: test level L, single wait time T, and single vent time T.
In the embodiment of the method corresponding to the first test content, the following describes the test experiment of this embodiment in detail by taking a group of values of the test parameters as an example, and the test experiment includes:
the preparation method comprises the following steps: demineralized water having a specified oxygen content is injected into the control tank, and the temperature of the liquid in the control tank is maintained constant by a steam heating system. Reference may be specifically made to the preparation steps of the method embodiment part corresponding to the test content, which are not described herein again.
A first testing step: adjusting the liquid level of a containing and controlling box to the testing liquid level, maintaining the stable flow of the upper charging flow and the stable flow and pressure of the lower discharging flow through the upper charging and lower discharging control unit, discharging gas in the containing and controlling box through the purging system, and maintaining the pressure in the containing and controlling box at a fourth preset pressure;
specifically, on the one hand, the charge-up pump is activated and the valve 033VP is opened, and the valve 046VP is adjusted to maintain the flow rate of the charge-up stream steady, on the other hand, the discharge pump is activated and the valves V1, V2, 013VP, 030VP1 are opened, and the valves V2 and 013VP maintain the flow rate and pressure of the discharge stream steady; and adjusting a pressure stabilizing valve 024VZ on the nitrogen purging pipeline to maintain the pressure in the volume control tank at a fourth preset pressure.
And a second testing step: and performing intermittent purging until the parameter monitoring system monitors that the oxygen content of the gas in the volume control box is stable, wherein the intermittent purging comprises the following steps: and controlling the gas in the containing and controlling box to be exhausted once according to the single exhaust time by the purging system every other single waiting time. Specifically, reference may be made to test step three of the method embodiment corresponding to the test content one, which is not described herein again.
And a third testing step: determining a time to perform the intermittent purge, and determining a change in an oxygen level of the liquid in the containment tank before and after performing the intermittent purge based on the parameter monitoring system. Specifically, reference may be made to test step four of the method embodiment corresponding to the test content one, which is not described herein again.
Corresponding to the fourth test content, another method embodiment of the present invention provides a nuclear power plant capacity control box oxygen removal test method, which is implemented based on the foregoing system embodiment, and the method of this embodiment includes the following steps:
the preparation method comprises the following steps: injecting the deaerated water into the control box, and maintaining the temperature of the liquid in the control box to be constant through a steam heating system; reference may be specifically made to the preparation steps of the method embodiment part corresponding to the second test content, which are not described herein again.
A first testing step: and maintaining the stable flow of the upper charging flow and the stable flow and pressure of the lower discharging flow through the upper charging and lower discharging control unit, and maintaining the pressure in the volume control box at a fifth preset pressure through the purging system. Specifically, reference may be made to the first testing step of the method embodiment portion corresponding to the second testing content, which is not described herein again.
And a second testing step: the flow rates of the upper filling flow and the lower discharging flow are controlled through the upper filling and lower discharging control unit, so that the liquid level of the containing and controlling box is raised to a first liquid level, the gas in the containing and controlling box is discharged through the purging system, and the pressure in the containing and controlling box is maintained at a sixth preset pressure. Specifically, reference may be made to the third testing step in the embodiment of the method corresponding to the second testing content, which is not described herein again.
And a third testing step: and the flow rates of the upper filling flow and the lower discharging flow are controlled by the upper filling and lower discharging control unit so that the liquid level of the containing and controlling box is reduced and maintained at a second liquid level. Specifically, reference may be made to test step four of the method embodiment portion corresponding to the test content two, which is not described herein again.
And a fourth testing step: and standing, wherein the oxygen content in the lower discharge flow is adjusted to a preset stable value through an oxygen content adjusting system in the standing process, and the change conditions of the oxygen content of the gas and the oxygen content of the liquid are recorded in real time based on the parameter monitoring system in the standing process. Specifically, reference may be made to test step five in the method embodiment portion corresponding to the test content two, which is not described herein again.
In summary, the nuclear power plant capacity control box deoxygenation testing system and method provided by the invention have the following beneficial effects: the testing system provided by the invention provides functions of flow control of upper charging flow and lower discharging flow, temperature regulation of lower discharging flow, oxygen content control of lower discharging flow, nitrogen supply, gas discharge and the like, and based on the functions, tests of 'intermittent blowing' and 'pressure-building exhaust' can be realized, and corresponding testing methods are respectively designed under different working conditions of 'intermittent blowing' and 'pressure-building exhaust' to test the oxygen removal effect of 'intermittent blowing' and 'pressure-building exhaust' on the volume control box, and the influence rule of key factors such as liquid level of the volume control box, single waiting time and single blowing time on the oxygen removal effect of 'intermittent blowing' is obtained through the tests; and obtaining the rule of influence of the standing time on the pressure-building exhaust oxygen removal effect through testing; and through comparison of test data of the two methods, the difference of the 'intermittent blowing' method and the 'pressure-holding exhaust' method in the deoxidization effect can be obtained, and a better data support is provided for adjustment of an actual unit deoxidization strategy.
While the present invention has been described with reference to the embodiments shown in the drawings, the present invention is not limited to the embodiments, which are illustrative and not restrictive, and it will be apparent to those skilled in the art that various changes and modifications can be made therein without departing from the spirit and scope of the invention as defined in the appended claims.
Claims (10)
1. The utility model provides a nuclear power plant's control box deoxidization test system which characterized in that includes:
the upper filling and lower discharging system comprises a buffer container, a lower discharging pipeline for guiding liquid in the buffer container into the containing and controlling box, an upper filling pipeline for guiding the liquid in the containing and controlling box back to the buffer container, and an upper filling and lower discharging control unit, wherein the upper filling and lower discharging control unit is used for controlling the flow and pressure of lower discharging flow in the lower discharging pipeline and upper filling flow in the upper filling pipeline;
the purging system is connected with the containing and controlling box and can be used for injecting nitrogen into the containing and controlling box and discharging gas in the containing and controlling box;
the oxygen content adjusting system is connected with the lower bleed pipeline and can be used for injecting oxygen into the lower bleed to adjust the oxygen content in the lower bleed;
the temperature control system is connected with the buffer container and is used for introducing heated steam into the liquid in the buffer container so as to adjust the temperature of the liquid;
and the parameter monitoring system is used for monitoring the flow, pressure and oxygen content of the lower discharge flow and the upper charging flow, and monitoring the pressure, liquid level, gas oxygen content and liquid oxygen content in the containing and controlling box.
2. The system of claim 1, wherein the top fill and bottom drain control unit comprises:
set up on filling the pipeline: the device comprises an upper charging pump, an upper charging isolation valve positioned on the upstream of the upper charging pump, and an upper charging flow regulating valve positioned on the downstream of the upper charging pump;
set up on the bleeder line: the lower bleed pump, a lower bleed isolation valve positioned at the upstream of the lower bleed pump and a lower bleed pressure reducing valve positioned at the downstream of the lower bleed pump, wherein the downstream of the lower bleed pressure reducing valve is connected with the oxygen content regulating system;
the buffer container comprises a bypass pipeline and a lower leakage flow regulating valve arranged on the bypass pipeline, wherein the bypass pipeline is connected between the downstream of the lower leakage flow reducing valve and the buffer container.
3. The system of claim 1, wherein the purging system comprises a nitrogen cylinder containing nitrogen, a nitrogen purge line connecting the nitrogen cylinder and the containment tank, a pressure stabilizing valve disposed on the nitrogen purge line, a vent line connecting the top of the containment tank, and a vent valve disposed on the vent line.
4. The system of claim 1, wherein the oxygen content adjustment system comprises: the air compressor is connected with a lower discharge pipeline through the aeration pipeline and is also connected with the top of the containing and controlling box through the containing and controlling box air injection pipeline.
5. The system of claim 1, wherein the parameter monitoring system comprises various sensors disposed in the upper fill and lower bleed system, nitrogen purge system, oxygen regulation system, and the containment tank that collect oxygen level, liquid level, flow, pressure, temperature data.
6. The system of claim 1, further comprising:
and the liquid injection system comprises a water replenishing pipeline connected with the bottom of the volume control box, a deoxidizing device arranged on the water replenishing pipeline, a water replenishing pump positioned on the downstream of the deoxidizing device, and a water replenishing valve positioned on the downstream of the water replenishing pump.
7. A nuclear power plant capacity control box deoxygenation testing method is realized based on the system of any one of claims 1-6, and is characterized by comprising the following steps: executing a plurality of test experiments based on a plurality of groups of values of the test parameters, wherein each test experiment is executed by taking one group of values of the test parameters; wherein, the test parameter includes test liquid level, single latency and single exhaust time, wherein, the test experiment includes:
the preparation method comprises the following steps: injecting desalted water with specified oxygen content into the control box, and maintaining the temperature of liquid in the control box to be constant through a steam heating system;
a first testing step: adjusting the liquid level of a containing and controlling box to the testing liquid level, controlling the flow of lower discharge and upper charge to be zero through the upper charge and lower discharge control unit, and maintaining the pressure in the containing and controlling box at a first preset pressure through the purging system;
and a second testing step: and performing intermittent purging until the parameter monitoring system monitors that the oxygen content of the gas in the volume control box is stable, wherein the intermittent purging comprises the following steps: controlling the gas in the containing and controlling box to be exhausted for one time according to the single exhausting time by the purging system every other single waiting time;
and a third testing step: determining a time to perform the intermittent purge, and determining a change in an oxygen level of the liquid in the containment tank before and after performing the intermittent purge based on the parameter monitoring system.
8. A nuclear power plant capacity control box deoxygenation testing method is realized based on the system of any one of claims 1-6, and is characterized by comprising the following steps:
the preparation method comprises the following steps: injecting the deaerated water into the control box, and maintaining the temperature of the liquid in the control box to be constant through a steam heating system;
a first testing step: maintaining the flow stability of the upper charging flow and the flow stability and pressure stability of the lower discharging flow through the upper charging and lower discharging control unit, and maintaining the pressure in the volume control box at a second preset pressure through the purging system;
and a second testing step: adjusting the oxygen content in the lower discharge flow to a preset stable value through an oxygen content adjusting system;
and a third testing step: controlling the flow rates of upper filling and lower discharging through the upper filling and lower discharging control unit so as to enable the liquid level of the containing and controlling box to be raised to a first liquid level, discharging gas in the containing and controlling box through the purging system, and maintaining the pressure in the containing and controlling box at a third preset pressure;
and a fourth testing step: controlling the flow rates of the upper filling flow and the lower discharging flow through the upper filling and lower discharging control unit so as to reduce the liquid level of the containing and controlling tank and maintain the liquid level at a second liquid level;
a fifth testing step: and standing, wherein the oxygen content in the lower discharge flow is adjusted to a preset stable value through an oxygen content adjusting system in the standing process, and the change conditions of the oxygen content of the gas and the oxygen content of the liquid are recorded in real time based on the parameter monitoring system in the standing process.
9. A nuclear power plant capacity control box deoxygenation testing method is realized based on the system of any one of claims 1-6, and is characterized by comprising the following steps: executing a plurality of test experiments based on a plurality of groups of values of the test parameters, wherein each test experiment is executed by taking one group of values of the test parameters; wherein, the test parameter includes test liquid level, single latency and single exhaust time, wherein, the test experiment includes:
the preparation method comprises the following steps: injecting desalted water with specified oxygen content into the control box, and maintaining the temperature of liquid in the control box to be constant through a steam heating system;
a first testing step: adjusting the liquid level of a containing and controlling box to the testing liquid level, maintaining the stable flow of the upper charging flow and the stable flow and pressure of the lower discharging flow through the upper charging and lower discharging control unit, discharging gas in the containing and controlling box through the purging system, and maintaining the pressure in the containing and controlling box at a fourth preset pressure;
and a second testing step: and performing intermittent purging until the parameter monitoring system monitors that the oxygen content of the gas in the volume control box is stable, wherein the intermittent purging comprises the following steps: controlling the gas in the containing and controlling box to be exhausted for one time according to the single exhausting time by the purging system every other single waiting time;
and a third testing step: determining a time to perform the intermittent purge, and determining a change in an oxygen level of the liquid in the containment tank before and after performing the intermittent purge based on the parameter monitoring system.
10. A nuclear power plant capacity control box deoxygenation testing method is realized based on the system of any one of claims 1-6, and is characterized by comprising the following steps:
the preparation method comprises the following steps: injecting the deaerated water into the control box, and maintaining the temperature of the liquid in the control box to be constant through a steam heating system;
a first testing step: maintaining the flow stability of the upper charging flow and the flow stability and pressure stability of the lower discharging flow through the upper charging and lower discharging control unit, and maintaining the pressure in the volume control box at a fifth preset pressure through the purging system;
and a second testing step: controlling the flow rates of upper flow filling and lower flow discharging through the upper flow filling and lower flow discharging control unit so that the liquid level of the containing and controlling box is raised to a first liquid level, discharging gas in the containing and controlling box through the purging system, and maintaining the pressure in the containing and controlling box at a sixth preset pressure;
and a third testing step: controlling the flow rates of the upper filling flow and the lower discharging flow through the upper filling and lower discharging control unit so as to reduce the liquid level of the containing and controlling tank and maintain the liquid level at a second liquid level;
and a fourth testing step: and standing, wherein the oxygen content in the lower discharge flow is adjusted to a preset stable value through an oxygen content adjusting system in the standing process, and the change conditions of the oxygen content of the gas and the oxygen content of the liquid are recorded in real time based on the parameter monitoring system in the standing process.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910011687.1A CN109741842B (en) | 2019-01-07 | 2019-01-07 | Nuclear power plant capacity control box deoxygenation testing system and method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910011687.1A CN109741842B (en) | 2019-01-07 | 2019-01-07 | Nuclear power plant capacity control box deoxygenation testing system and method |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN109741842A CN109741842A (en) | 2019-05-10 |
| CN109741842B true CN109741842B (en) | 2020-09-22 |
Family
ID=66363540
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201910011687.1A Active CN109741842B (en) | 2019-01-07 | 2019-01-07 | Nuclear power plant capacity control box deoxygenation testing system and method |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN109741842B (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110608843B (en) * | 2019-08-21 | 2021-02-09 | 岭澳核电有限公司 | Method, device, equipment and medium for measuring pressure of arc extinguish chamber of nuclear power station switch equipment |
| CN110752045B (en) * | 2019-10-24 | 2021-03-26 | 西安交通大学 | Purging system and method for volume control box of nuclear power station |
| CN113782236B (en) * | 2021-09-09 | 2024-01-16 | 哈尔滨工程大学 | Test device for researching quick start of nuclear reactor |
Family Cites Families (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103811089B (en) * | 2012-11-13 | 2016-08-03 | 中国广核集团有限公司 | A kind of nuclear power station secondary loop oxygen-eliminating device and liquid level controlling method thereof |
| JP2015087350A (en) * | 2013-11-01 | 2015-05-07 | 原子燃料工業株式会社 | Nuclear fuel sipping device and nuclear fuel sipping method |
| CN104090592B (en) * | 2014-06-27 | 2019-03-26 | 中广核工程有限公司 | The control method of oxygen content in nuclear power station cooling agent circuit |
| CN204237586U (en) * | 2014-11-28 | 2015-04-01 | 哈尔滨锅炉厂有限责任公司 | Nuclear power auxiliary feedwater system dividing wall type deoxygenator |
| KR101722513B1 (en) * | 2015-06-30 | 2017-04-19 | 한국수력원자력 주식회사 | Cooling tower basin cooling system and cooling method |
| CN105551534A (en) * | 2015-11-13 | 2016-05-04 | 中国核动力研究设计院 | Reactor coolant chemical and volume control system and control method thereof |
| CN105448370B (en) * | 2015-11-18 | 2018-05-01 | 中广核工程有限公司 | A kind of nuclear power station rinses and water replanishing device and method |
| CN106847349A (en) * | 2016-11-25 | 2017-06-13 | 深圳中广核工程设计有限公司 | One loop of nuclear power station cooling agent high-pressure hydrogenation system |
-
2019
- 2019-01-07 CN CN201910011687.1A patent/CN109741842B/en active Active
Also Published As
| Publication number | Publication date |
|---|---|
| CN109741842A (en) | 2019-05-10 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN109741842B (en) | Nuclear power plant capacity control box deoxygenation testing system and method | |
| CN110182924B (en) | Full-automatic ammonia preparing and adding integrated machine device and full-automatic ammonia preparing and adding method | |
| CN110783006B (en) | Degassing test device and method | |
| CN109932272B (en) | CO (carbon monoxide) 2 Displacement experiment system and displacement experiment method | |
| CN106523916A (en) | High-flow liquid medium combined supply system | |
| CN105628387B (en) | Using the adjustment method of PREDICTIVE CONTROL method regulation test bay air-suction state parameter | |
| CN102054537A (en) | Nuclear class-1 equipment performance test system and method | |
| CN110752045B (en) | Purging system and method for volume control box of nuclear power station | |
| CN110379526A (en) | Pressurized water reactor nuclear island container blowing method and row's hydrogen purge system | |
| CN109166638A (en) | A kind of coolant hydrogenation system and method for small-sized heap | |
| CN114843556A (en) | Hydrogen circulating pump and ejector performance test system | |
| CN116525890A (en) | Off-line calibration device and off-line calibration method for hydrogen circulation system for fuel cell | |
| CN115274148A (en) | Nuclear power plant containment tightness simulation test system | |
| CN208752973U (en) | A kind of offline cooling back installation for spent fuel transport container | |
| CN204177558U (en) | A kind of big-flow high-pressure fluid test system | |
| CN115045869A (en) | Automatic air supply control method for pressure tank based on Boyle function fitting | |
| CN217468507U (en) | Hydrogen circulating pump and ejector performance test system | |
| CN113782236B (en) | Test device for researching quick start of nuclear reactor | |
| CN209117350U (en) | A kind of engine thermal is on probation to blow water system | |
| CN112556768A (en) | Oil consumption measuring device and method for high-horsepower diesel generator set in multi-bubble state | |
| CN220393690U (en) | Carbon dioxide providing equipment for pickling full-ecological pickled Chinese cabbage | |
| CN113447401B (en) | Water intake connecting pipe multiphase flow test system and method for residual water system of small nuclear reactor | |
| CN210378084U (en) | Thermotechnical liquid level adjustment simulation tool | |
| CN117782471B (en) | Device and method for detecting conduction capacity of argon blowing pipeline of RH vacuum tank dip pipe | |
| KR102629816B1 (en) | Hydrogenation system and method for pressurized water reactor |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |