CN117423485A - Simulation experiment device and simulation experiment method for direct safety injection by-pass flow of reactor - Google Patents
Simulation experiment device and simulation experiment method for direct safety injection by-pass flow of reactor Download PDFInfo
- Publication number
- CN117423485A CN117423485A CN202311259329.5A CN202311259329A CN117423485A CN 117423485 A CN117423485 A CN 117423485A CN 202311259329 A CN202311259329 A CN 202311259329A CN 117423485 A CN117423485 A CN 117423485A
- Authority
- CN
- China
- Prior art keywords
- steam
- reactor
- simulation
- water
- simulator
- 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.)
- Pending
Links
- 238000004088 simulation Methods 0.000 title claims abstract description 107
- 238000002347 injection Methods 0.000 title claims abstract description 29
- 239000007924 injection Substances 0.000 title claims abstract description 29
- 238000000034 method Methods 0.000 title claims abstract description 16
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 134
- 238000005259 measurement Methods 0.000 claims abstract description 45
- 230000005514 two-phase flow Effects 0.000 claims abstract description 30
- 230000001502 supplementing effect Effects 0.000 claims abstract description 15
- 238000012360 testing method Methods 0.000 claims description 24
- 230000001105 regulatory effect Effects 0.000 claims description 22
- 239000007788 liquid Substances 0.000 claims description 21
- 238000001816 cooling Methods 0.000 claims description 18
- 238000009826 distribution Methods 0.000 claims description 8
- 238000010438 heat treatment Methods 0.000 claims description 7
- 238000005303 weighing Methods 0.000 claims description 7
- 229920006395 saturated elastomer Polymers 0.000 claims description 6
- 238000002360 preparation method Methods 0.000 claims description 4
- 238000007789 sealing Methods 0.000 claims description 4
- 239000012808 vapor phase Substances 0.000 claims description 4
- 239000008367 deionised water Substances 0.000 claims description 3
- 229910021641 deionized water Inorganic materials 0.000 claims description 3
- 238000012423 maintenance Methods 0.000 abstract description 5
- 238000002474 experimental method Methods 0.000 description 11
- 239000007789 gas Substances 0.000 description 7
- 239000002826 coolant Substances 0.000 description 5
- 238000010926 purge Methods 0.000 description 5
- 239000000498 cooling water Substances 0.000 description 4
- 230000008021 deposition Effects 0.000 description 4
- 239000012071 phase Substances 0.000 description 3
- 239000013589 supplement Substances 0.000 description 3
- 238000010793 Steam injection (oil industry) Methods 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000003860 storage Methods 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000008236 heating water Substances 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 238000005304 joining Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
-
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention relates to a direct safety injection side flow simulation experiment device and a simulation experiment method of a reactor, wherein the direct safety injection side flow simulation experiment device of the reactor comprises the following components: the reactor simulator comprises a simulator body, a steam pipeline, a circulating pipeline and an output pipeline; the steam simulation system is connected with the reactor simulator through the steam pipeline; the two-phase flow measurement system is connected with the reactor simulator through the output pipeline; the water replenishing system comprises a direct water replenishing system and an indirect water replenishing system, and the direct water replenishing system is respectively connected with the steam simulation system and the circulating pipeline; the indirect water supplementing system is connected to the reactor simulator. Because the reactor simulator can simulate the internal conditions of the reactor, the steam simulation system, the two-phase flow measurement system and the water supplementing system can simulate the internal environment of the reactor accident, so that the reactor accident can be simulated, and the operation and maintenance level of the nuclear power station can be improved.
Description
Technical Field
The application relates to the technical field of nuclear reactor hydraulic experiments, in particular to a reactor direct safety injection bypass flow simulation experiment device and a simulation experiment method.
Background
In the operation and maintenance of a nuclear power plant, accident handling for the nuclear reactor often requires ensuring the effectiveness of the handling means. For large breach water loss incidents in direct injection type reactors, the process of handling the incident typically includes a refill phase and a refill phase.
In the water refilling stage, the coolant of the direct injection type reactor may be affected by the reverse flow of steam in the descending annular cavity, so that the coolant for the reactor flows out from the break and cannot enter the reactor core, and thus the reactor core cannot be cooled normally, and the phenomenon of countercurrent flow restriction is caused. During the re-flooding phase, the reactor coolant may be affected by the lateral flow of steam in the cold leg of the intact loop, and the coolant may not smoothly enter the core, resulting in direct bypass. As the liquid level of the annular cavity is gradually restored, the intact cold-section steam can be purged, and the water at the upper part of the entrained liquid level is discharged from the break, so that the phenomenon of purging bypass is caused.
When the above countercurrent flow restriction phenomenon, direct bypass flow phenomenon or purge bypass flow phenomenon occurs, the injection efficiency of the coolant is affected, thereby causing uncontrollable core temperature and even melting burnout of the core, and threatening the safety and integrity of the reactor vessel and the internals. Therefore, in order to avoid the occurrence of the above situation, a reactor direct safety injection bypass flow simulation experiment needs to be performed to the operation and maintenance level of the nuclear power plant; however, there is no experimental apparatus capable of performing the above-described simulation experiment.
Disclosure of Invention
The technical problem to be solved by the application is to provide a reactor direct safety injection bypass flow simulation experiment device and a simulation experiment method.
The technical scheme adopted for solving the technical problems is as follows: constructing a direct safety injection side flow simulation experiment device of a reactor, comprising:
the reactor simulator is used for simulating the conditions in the reactor and comprises a simulator body, and a steam pipeline, a circulating pipeline and an output pipeline which are connected to the simulator body;
the steam simulation system is connected with the reactor simulator through the steam pipeline;
the two-phase flow measurement system is connected with the reactor simulator through the output pipeline; and;
the water replenishing system comprises a direct water replenishing system and an indirect water replenishing system, and the direct water replenishing system is respectively connected with the steam simulation system and the circulating pipeline and is connected with the reactor simulation body through the circulating pipeline; the indirect water supplementing system is connected with the reactor simulator through the circulating pipeline.
In some embodiments, the steam simulation system comprises a first steam generating device and a second steam generating device, the steam lines comprising a first steam line, a second steam line, and a third steam line, the first steam generating device being connected to the first steam line; the second steam generating device is connected with the second steam pipeline and the third steam pipeline; the first steam pipeline, the second steam pipeline and the third steam pipeline are connected to the simulation body.
In some embodiments, the first steam generating device comprises a first flowmeter, the steam simulation system further comprises a converging pipeline, the steam generated by the first steam generating device and the steam generated by the second steam generating device are converged through the converging pipeline and flow into the simulation body through the first flowmeter, and a stop valve is further arranged on the converging pipeline.
In some embodiments, the two-phase flow measurement system includes a shut-off valve and a steam-water separator coupled to the shut-off valve, the steam-water separator including a steam output and a water output; the two-phase flow measurement system further comprises a gas measurement system and a liquid measurement system, wherein the gas measurement system comprises a flowmeter, a regulating valve and a stop valve which are sequentially connected, and the two-phase flow measurement system further comprises a flowmeter, a regulating valve and a stop valve which are arranged in parallel with the flowmeter, the regulating valve and the stop valve.
In some embodiments, the liquid measurement system includes a flow distribution valve and first and second weigh tanks connected to the output of the flow distribution valve, respectively.
In some embodiments, the indirect water replenishment system comprises a first cooling circulation line connected to the simulator body, comprising a shut-off valve, a water pump, a heat exchanger, a shut-off valve, a flow meter, and a shut-off valve connected in sequence; the first cooling circulation pipeline further comprises regulating valves respectively connected to the heat exchanger and two ends of the stop valve.
In some embodiments, the indirect water replenishment system comprises a second cooling circulation line connected to the simulator body, comprising a shut-off valve, a water pump, a heat exchanger, a shut-off valve, a flow meter, and a shut-off valve connected in sequence; the second cooling circulation pipeline further comprises regulating valves respectively connected to the heat exchanger and two ends of the stop valve.
The simulation experiment method is used for the reactor direct injection bypass flow simulation experiment device, and comprises the following steps:
s1: checking before test; developing a sealing test, and checking the tightness of the reactor simulator, the steam simulation system, the two-phase flow measurement system and the water supplementing system;
s2: preparing before testing; enabling the reactor simulator to achieve the state of simulating the reactor;
s3: reaching target parameters; adjusting parameters of steam, water temperature, water level, power and pressure according to the test purpose;
s4: carrying out a test; recording temperature, pressure difference, voltage, current, flow, liquid level, quality and dryness parameters.
In some embodiments, the S2: the pre-test preparation step includes the following sub-steps:
s21: water injection and exhaust; injecting water into the two-phase flow measurement system and the water supplementing system, exhausting, and then filling water into the reactor simulation body and the steam simulation system;
s22: establishing a reactor simulator vapor phase space; starting a steam simulation system, and communicating the steam simulation system with a reactor simulator when the deionized water is heated to a saturation temperature; heating power of a steam simulation system is increased, saturated water is heated to generate saturated steam, and the liquid level in the reactor simulation body reaches a preset liquid level;
s23: preheating a reactor simulator; and communicating the reactor simulant with the two-phase flow measurement system to preheat the reactor simulant to a predetermined temperature.
In some embodiments, the simulation experiment method further comprises the steps of:
s5: and (5) reducing the temperature and the pressure, and gradually reducing the heating power of the steam simulation system after test data are acquired.
The implementation of the invention has at least the following beneficial effects: because the reactor simulator can simulate the internal conditions of the reactor, the steam simulation system, the two-phase flow measurement system and the water supplementing system can simulate the internal environment of the reactor accident, so that the reactor accident can be simulated, and the operation and maintenance level of the nuclear power station can be improved.
Drawings
The application will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is a schematic diagram of a piping structure of a simulation experiment apparatus in some embodiments of the present application.
Detailed Description
For a clearer understanding of technical features, objects, and effects of the present application, a detailed description of specific embodiments of the present application will be made with reference to the accompanying drawings. In the following description, it should be understood that the directions or positional relationships indicated by "front", "rear", "upper", "lower", "left", "right", "longitudinal", "transverse", "vertical", "horizontal", "top", "bottom", "inner", "outer", "head", "tail", etc. are configured and operated in specific directions based on the directions or positional relationships shown in the drawings, are merely for convenience of describing the present invention, and do not indicate that the apparatus or element referred to must have specific directions, and thus should not be construed as limiting the present application.
It should also be noted that unless explicitly stated or limited otherwise, terms such as "mounted," "connected," "secured," "disposed," and the like are to be construed broadly and may be, for example, fixedly connected, detachably connected, or integrally formed; can be mechanically or electrically connected; can be directly connected or indirectly connected through an intermediate medium, and can be communicated with the inside of two elements or the interaction relationship of the two elements. When an element is referred to as being "on" or "under" another element, it can be "directly" or "indirectly" on the other element or one or more intervening elements may also be present. The terms "first," "second," "third," and the like are used merely for convenience in describing the present invention and are not to be construed as indicating or implying a relative importance or implicitly indicating the number of technical features indicated, whereby features defining "first," "second," "third," etc. may explicitly or implicitly include one or more such features. The specific meaning of the terms in this application will be understood by those of ordinary skill in the art as the case may be.
In the following description, for purposes of explanation and not limitation, specific details are set forth, such as particular system configurations, techniques, etc. in order to provide a thorough understanding of the embodiments of the present application. It will be apparent, however, to one skilled in the art that the present application may be practiced in other embodiments that depart from these specific details. In other instances, detailed descriptions of well-known systems, devices, circuits, and methods are omitted so as not to obscure the description of the present application with unnecessary detail.
A reactor direct safety bypass simulation experiment device 1 in some embodiments of the present invention is shown in fig. 1, and the reactor direct safety bypass simulation experiment device 1 may be used to simulate a safety bypass experiment to develop a countercurrent flow restriction experiment, a direct bypass experiment, or a purge bypass experiment for a reactor.
The reactor direct safety injection by-pass flow simulation experiment device 1 may include a reactor simulator 10, a steam simulation system 20, a two-phase flow measurement system 30, a water replenishment system 40, a instrumentation system 50, and an electrical system 60 in some embodiments. The reactor simulator 10 may be used in some embodiments to simulate a reactor to simulate the flow of liquids and/or gases within the reactor. The steam simulation system 20 is connected to the reactor simulator 10, and generates steam and transmits the steam to the reactor simulator 10, thereby providing the reactor simulator 10 with steam required for a counter-current flow restriction experiment, a direct bypass experiment, or a purge run bypass experiment. The two-phase flow measurement system 30 is connected to the reactor simulator 10, and steam and/or liquid flowing out through the reactor simulator 10 can flow into the two-phase flow measurement system 30, and the two-phase flow measurement system 30 can measure the flow of steam and/or liquid, so as to obtain experimental data of a countercurrent flow restriction experiment, a direct bypass experiment or a purge bypass experiment of the reactor performed by the reactor simulator 10.
The water replenishing system 40 is connected to the reactor simulator 10 and the steam simulation system 20, and is capable of replenishing the reactor simulator 10 and the steam simulation system 20 with liquid, ensuring the continuity of steam generation of the steam simulation system 20, and replenishing the reactor simulator 10 with liquid, so that the reactor simulator 10 can perform simulation experiments smoothly. The control system 50 and the electrical system 60 are respectively connected to the reactor simulator 10, the steam simulation system 20, the two-phase flow measurement system 30 and the water supplementing system 40, so that the safety and convenience are improved when a user operates the reactor direct injection bypass flow simulation experiment device 1.
The reactor simulator 10 may in some embodiments include a simulator body 100 and vapor line 101, recycle line 102, and output line 103 connected to the simulator body 100. The steam pipe 101 is connected to the steam simulation system 20 and the simulation body 100, and can transfer steam generated in the steam simulation system 20 into the simulation body 100. The circulation pipeline 102 is connected to the water replenishing system 40 and the simulation body 100, and can cool the water deposited by the simulation body 100 and re-input the water into the simulation body 100, thereby realizing the operation of circulating the water replenishing and filling for the simulation body 100. The output pipeline 103 is connected to the two-phase flow measurement system 30 and the simulator body 100, respectively, and can output the steam and the liquid output after the simulator body 100 simulates the reactor to the two-phase flow measurement system 30, so as to realize measurement of experimental results, thereby completing simulation experiments on the reactor.
Specifically, the steam line 101 may include a first steam line 1011, a second steam line 1012, and a third steam line 1013, respectively, connected to the simulator body 100 in some embodiments. The circulation line 102 may include, in some embodiments, a first circulation line 1021 output from the simulator body 100 and second and third circulation lines 1022, 1023 input to the simulator body 100. The first circulation pipeline 1021 is connected to the water replenishing system 40, and guides the water generated by the water replenishing system 40 into the simulation body 100, so as to realize the water replenishing operation of the simulation body 100.
The steam simulation system 20 may in some embodiments comprise a first steam generating means 21 and a second steam generating means 22. The first steam generating device 21 is connected to the first steam line 1011; the second steam generating device 22 is connected to the second steam line 1012 and the third steam line 1013, respectively, so as to input the generated steam into the simulation body 100. Specifically, due to the construction of the dummy body 100, the second steam generating device 22 needs to input steam from the second steam line 1012 and the third steam line 1013, respectively, to the inside thereof. The third steam line 1013 is also provided with a flow meter and a shut-off valve to control the output steam flow.
The first steam generating device 21 may include, in some embodiments, a first steam generator 211, a first relief valve 212 coupled to the first steam generator 211, a first shut-off valve 213 coupled to the first steam generator 211, and a first flowmeter 214 coupled to the first steam generator 211.
Wherein the first steam generator 211 is used for heating water to form steam, so as to obtain steam required by simulation; the first safety valve 212 can release pressure when the internal pressure of the first steam generator 211 is too high, so as to ensure safe operation of the first steam generator 211; the first stop valve 213 can be used to open or close the pipeline for delivering the steam generated by the first steam generator 211 to the simulator body 100; the first flowmeter 214 is installed on a pipeline for delivering the steam generated by the first steam generator 211 to the simulator body 100, and can be used for measuring the steam output by the first steam generating device 21.
The second steam generating device 22 may include, in some embodiments, a second steam generator 221, a second relief valve 222 coupled to the second steam generator 221, a second shut-off valve 223 coupled to the second steam generator 221, and a second flowmeter 224 coupled to the second steam generator 221.
Wherein the second steam generator 221 is operable to heat water to form steam, thereby obtaining steam required for simulation; the second safety valve 222 can release pressure when the internal pressure of the second steam generator 221 is too high, so as to ensure safe operation of the second steam generator 221; the second stop valve 223 may be used to open or close a pipe through which the steam generated by the second steam generator 221 is delivered to the simulator body 100; the second flowmeter 224 is installed on a pipeline through which the steam generated by the second steam generator 221 is delivered to the simulator body 100, and can be used to measure the amount of steam output by the second steam generating device 22.
In some embodiments, the steam simulation system 20 further includes a converging line 2202 through which the steam generated by the first steam generator 211 and the second steam generator 221 can converge and flow into the simulator body 100 via the first flow meter 214 in the first steam generating device 21. The confluence pipe 2202 is further provided with a shutoff valve 2203.
Specifically, when the joining is required, the first shut-off valve 213 and the shut-off valve 2203 are in an open state, the second shut-off valve 223 is in a closed state, and the output pipe 2201 is in a closed state; at this time, the flow rate measured by the first flow meter 214 is the sum of the steam flow rates output by the first steam generating device 21 and the second steam generating device 22. When the flow into the dummy body 100 is required, the first stop valve 213 and the second stop valve 223 are opened, and the stop valve 2203 is closed; at this time, the first flowmeter 214 and the second flowmeter 224 measure the steam flow rate output by the first steam generating device 21 and the second steam generating device 22, respectively.
The two-phase flow measurement system 30 is connected to the output line 103, which in some embodiments may include a shut-off valve 301 and a vapor-water separator 302 connected to the shut-off valve 301. The steam-water separator 302 may output steam and water, respectively, and includes a steam output and a water output. The steam-water separator 302 is further provided with a safety valve 303 to prevent the occurrence of safety risk due to excessive pressure in the steam-water separator 302.
At the steam output, the two-phase flow measurement system 30 further comprises a gas measurement system comprising a flow meter 304, a regulating valve 305, a shut-off valve 306, connected in sequence. The steam sequentially flows through the flow meter 304, the regulating valve 305, and the shut-off valve 306 to measure the amount of steam generated by the dummy body 100. In some embodiments, the gas measurement system is further provided with a flowmeter 307, a regulating valve 308 and a stop valve 309 connected in parallel with the pipelines of the flowmeter 304, the regulating valve 305 and the stop valve 306, which are sequentially connected, and when the steam flow is large, the steam flow can be measured through two steam channels, so that a more accurate steam flow value is obtained. The gas measurement system in some embodiments further comprises a heat exchanger 310 connected to the end of the shut-off valve 306 and shut-off valve 309 to cool the output steam to liquefy and flow it into the make-up system 40 for circulation. Further, the gas measurement system also includes a flow meter 311 and a shut-off valve 312 connected to the heat exchanger 310, which can be used to direct water generated by condensing steam into the water replenishment system.
At the water output, the two-phase flow measurement system 30 further comprises a liquid measurement system comprising a flow distribution valve 313, and a first weigh tank 314 and a second weigh tank 315 respectively connected to the outputs of the flow distribution valve 313. A flow meter 316 and a flow meter 317 are respectively provided between the flow distribution valve 313 and the first and second weigh tanks 314 and 315 to measure the flow of the liquid flowing into the first and second weigh tanks 314 and 315. The first weighing water tank 314 and the second weighing water tank 315 are further connected to the flow distribution valve 313 through a balance pipeline stop valve 318 and a balance pipeline stop valve 319 respectively so as to keep the pressure in the first weighing water tank 314 and the second weighing water tank 315 stable, thereby ensuring the accuracy of weighing obtained data.
The water replenishment system 40 may include a direct water replenishment system 41 and an indirect water replenishment system 42 in some embodiments. The direct water replenishment system 41 may replenish the outside water directly to the reactor simulator 10 or the steam simulator 20. The indirect water replenishment system 42 may cool the deposition water output from the reactor simulator 10 and re-input the cooled deposition water into the reactor simulator 10, the indirect water replenishment system 42 being connected to the circulation line 102.
The direct water replenishment system 41 may in some embodiments include a water storage tank 410 and a first water replenishment line 411, a second water replenishment line 412, and a third water replenishment line 413 connected to the water storage tank 410, respectively. The first water supplementing pipe 411 is connected to the first steam generator 211 of the first steam generating device 21 to supplement the first steam generator 211 with water required for generating steam; the second water supplementing pipe 412 is connected to the second steam generator 221 of the second steam generating device 22 to supplement the second steam generator 221 with water required for generating steam. The third water supplementing pipeline 413 is indirectly connected to the simulation body 100 through a first circulating pipeline 1021 to supplement water required by the simulation experiment for the simulation body 100. The water tank 410 is further provided with a safety valve 4100 for releasing pressure when the internal pressure of the water tank 410 is too high, so as to ensure safe operation of the water tank 410.
The first make-up line 411 may include, in some embodiments, a shut-off valve 4111, a water pump 4112, a flow meter 4113, and a shut-off valve 4114 disposed in line order. The second water replenishment line 412 may in some embodiments include a shut-off valve 4121, a water pump 4122, a flow meter 4123, and a shut-off valve 4124 disposed in line order. The third water replenishment line 413 may include a shut-off valve 4131, a water pump 4132, a flow meter 4133, and a shut-off valve 4134, in series along the line in some embodiments.
Specifically, the shutoff valves 4111 and 4114, the shutoff valves 4121 and 4124, and the shutoff valves 4131 and 4134 may be used to control the opening or closing of the first, second, and third water replenishment lines 411, 412, and 413, respectively; closing the shutoff valves 4111 and 4114 simultaneously, closing the shutoff valves 4121 and 4124 simultaneously, or closing the shutoff valves 4131 and 4134 simultaneously may facilitate maintenance or disassembly operations of the water pump 4112 and the flow meter 4113, the water pump 4122 and the flow meter 4123, or the water pump 4132 and the flow meter 4133, respectively.
The indirect water replenishment system 42 may, in some embodiments, include a first cooling circulation line connected to the analog body 100 that includes a shut-off valve 4201, a water pump 4202, a heat exchanger 4203, a shut-off valve 4204, a flow meter 4205, and a shut-off valve 4206 connected in sequence. The deposition water outputted from the reactor simulator 10 is re-inputted to the reactor simulator 10 through the shut-off valve 4201, the water pump 4202, the heat exchanger 4203, the shut-off valve 4204, the flow meter 4205, and the shut-off valve 4206 in this order.
In some embodiments, the first cooling circuit further comprises a regulating valve 4207 connected to both ends of the heat exchanger 4203 and the stop valve 4204, respectively, the regulating valve 4207 being operable to regulate heat exchange efficiency of the heat exchanger 4203. The first cooling circulation line further comprises a stop valve 4208 and a flow meter 4209 connected to the heat exchanger 4203, and cooling water generated in the circulating cooling water system can enter the heat exchanger 4203 through the stop valve 4208 and the flow meter 4209 for heat exchange and cooling.
The indirect water replenishment system 42 further includes a second cooling circulation line that may include a shut-off valve 4211, a water pump 4212, a heat exchanger 4213, a shut-off valve 4214, a flow meter 4215, and a shut-off valve 4216 connected in sequence. The deposition injection water outputted from the reactor simulator 10 flows into the reactor simulator 10 again after passing through the stop valve 4211, the water pump 4212, the heat exchanger 4213, the stop valve 4214, the flow meter 4215 and the stop valve 4216 in order, thereby realizing the simulation of the injection flow.
In some embodiments, the second cooling circuit further includes a regulating valve 4217 connected to both ends of the heat exchanger 4213 and the stop valve 4214, respectively, the regulating valve 4217 being operable to regulate the heat exchange efficiency of the heat exchanger 4213. The second cooling circulation line further includes a stop valve 4218 and a flow meter 4219 connected to the heat exchanger 4213, and the mixture of cooling water in the circulating cooling water system can enter the heat exchanger 4213 through the stop valve 4218 and the flow meter 4219 and exchange heat and cool.
The invention also discloses a simulation experiment method of the reactor direct safety injection bypass flow simulation experiment device 1. The simulation experiment method may include the following steps in some embodiments:
s1: checking before the test.
The states of the reactor simulator 10, the steam simulation system 20, the two-phase flow measurement system 30, the water replenishment system 40, the instrumentation system 50, and the electrical system 60 are checked for the presence of test conditions. Specifically, a sealing test may be performed to check whether the sealing properties of the reactor simulator 10, the steam simulation system 20, the two-phase flow measurement system 30, and the water replenishment system 40 are good.
S2: preparation before testing, so that the reactor simulator 10 reaches a state of simulating a reactor;
this pre-test preparation step in some embodiments includes the steps of:
s21: and (5) water injection and air exhaust. The two-phase flow measurement system 30 and the water replenishment system 40 are filled with water, and the system equipment and meters are exhausted, and then the reactor simulator 10 and the steam simulation system 20 are filled with water.
S22: a vapor phase space of the reactor simulator 10 is established. The steam simulation system 20 is started and when the deionized water is heated to the saturation temperature, the steam simulation system 20 and the reactor simulator 10 are communicated. The heating power of the steam simulation system 20 is increased, saturated water is heated to generate saturated steam, and the drain valve of the reactor simulator 10 is opened to drain to a predetermined level, and then closed, thereby establishing a vapor phase space of the reactor simulator 10.
S23: the reactor simulators are preheated. And the reactor simulators are communicated with the steam-water separator, the steam outlet pipeline valve is fully opened, and the reactor simulators are preheated to a preset temperature by high-temperature steam generated by the steam generating device.
S3: the target parameters are reached.
The cut-off valves on the first steam generating device 21 and the second steam generating device 22 are adjusted according to the test purpose to realize different steam injection modes;
adjusting the steam injection flow rate by adjusting the heating power of the first steam generating device 21 and the second steam generating device 22;
adjusting the flow rate by adjusting the frequency of the water pump 4202 and the water pump 4212 in the indirect water replenishment system 42;
the water injection temperature regulation is realized through regulating the regulating valve 4207 and the regulating valve 4217;
regulating the system pressure by adjusting steam outlet line shut-off valve 306, shut-off valve 309;
the drop-down annulus level is adjusted by adjusting the feed pump 4132 flow.
And adjusting the parameters until each parameter reaches the target parameter, thereby meeting the test requirement.
S4: and (5) carrying out a test.
When the parameters of each system and equipment meet the test requirements, the corresponding test program is executed by a computer of the measurement and control system to automatically record the parameters such as temperature, pressure difference, voltage, current, flow, liquid level, quality, dryness and the like, so that the safety and side flow characteristics of the descending annular chamber DVI of the reactor can be analyzed.
S5: cooling and reducing pressure.
After test data are acquired, the heating power of the steam generating device is gradually reduced, and then the cooling and the pressure reduction of the loop system are realized until the target value is reached.
It is to be understood that the above examples represent only some embodiments of the invention, which are described in more detail and are not to be construed as limiting the scope of the invention; it should be noted that, for a person skilled in the art, the above technical features can be freely combined, and several variations and modifications can be made without departing from the scope of the invention; therefore, all changes and modifications that come within the meaning and range of equivalency of the claims are to be embraced within their scope.
Claims (10)
1. A reactor direct safety injection by-pass flow simulation experiment device, comprising:
a reactor simulator (10) for simulating an in-reactor situation, comprising a simulator body (100) and a steam line (101), a circulation line (102) and an output line (103) connected to the simulator body (100);
a steam simulation system (20) connected to the reactor simulator (10) by the steam line (101);
-a two-phase flow measurement system (30) connected to said reactor simulator (10) by means of said output line (103); and
a water replenishing system (40), wherein the water replenishing system (40) comprises a direct water replenishing system (41) and an indirect water replenishing system (42), and the direct water replenishing system is respectively connected with the steam simulation system (20) and a circulating pipeline (102) and is connected with the reactor simulation body (10) through the circulating pipeline (102); the indirect water supplementing system (42) is connected to the reactor simulator (10) through the circulation pipeline (102).
2. The reactor direct safety injection bypass flow simulation experiment device according to claim 1, wherein the steam simulation system (20) comprises a first steam generating device (21) and a second steam generating device (22), the steam line (101) comprises a first steam line (1011), a second steam line (1012) and a third steam line (1013), the first steam generating device (21) is connected to the first steam line (1011); the second steam generating device (22) is connected to the second steam pipeline (1012) and the third steam pipeline (1013); the first steam line (1011), the second steam line (1012), and the third steam line (1013) are connected to the dummy body (100).
3. The direct safety injection bypass flow simulation experiment device for a reactor according to claim 2, wherein the first steam generating device (21) comprises a first flowmeter (214), the steam simulation system (20) further comprises a converging pipeline (2202), the steam generated by the first steam generating device (21) and the second steam generating device (22) is converged through the converging pipeline (2202) and flows into the simulation body (100) through the first flowmeter (214), and a stop valve (2203) is further arranged on the converging pipeline (2202).
4. The direct safety injection bypass flow simulation experiment device of a reactor according to claim 1, wherein the two-phase flow measurement system (30) comprises a stop valve (301) and a steam-water separator (302) connected to the stop valve (301), the steam-water separator (302) comprising a steam output end and a water output end; the two-phase flow measurement system (30) further comprises a gas measurement system and a liquid measurement system, wherein the gas measurement system comprises a flowmeter (304), a regulating valve (305) and a stop valve (306) which are sequentially connected, and the two-phase flow measurement system further comprises a flowmeter (307), a regulating valve (308) and a stop valve (309) which are arranged in parallel with the flowmeter (304), the regulating valve (305) and the stop valve (306).
5. The direct safety injection bypass flow simulation experiment device for a reactor according to claim 4, wherein the liquid measurement system comprises a flow distribution valve (313), and a first weighing water tank (314) and a second weighing water tank (315) respectively connected to the output ends of the flow distribution valve (313).
6. The direct safety injection bypass flow simulation experiment device of a reactor according to claim 1, wherein the indirect water supplementing system (42) comprises a first cooling circulation pipeline connected to the simulation body (100), which comprises a stop valve (4201), a water pump (4202), a heat exchanger (4203), a stop valve (4204), a flow meter (4205) and a stop valve (4206) connected in sequence; the first cooling circulation line further includes a regulating valve (4207) connected to both ends of the heat exchanger (4203) and the shut-off valve (4204), respectively.
7. The direct safety injection bypass flow simulation experiment device of a reactor according to claim 6, wherein the indirect water supplementing system (42) comprises a second cooling circulation pipeline connected to the simulation body (100), and the second cooling circulation pipeline comprises a stop valve (4211), a water pump (4212), a heat exchanger (4213), a stop valve (4214), a flowmeter (4215) and a stop valve (4216) which are connected in sequence; the second cooling circulation pipeline further comprises a regulating valve (4217) which is respectively connected to the two ends of the heat exchanger (4213) and the stop valve (4214).
8. A simulation experiment method for the reactor direct safety injection bypass flow simulation experiment apparatus as set forth in any one of claims 1 to 7, wherein the simulation experiment method comprises the steps of:
s1: checking before test; developing a sealing test, and checking the tightness of the reactor simulator (10), the steam simulation system (20), the two-phase flow measurement system (30) and the water supplementing system (40);
s2: preparing before testing; enabling the reactor simulator (10) to achieve a state simulating a reactor;
s3: reaching target parameters; adjusting parameters of steam, water temperature, water level, power and pressure according to the test purpose;
s4: carrying out a test; recording temperature, pressure difference, voltage, current, flow, liquid level, quality and dryness parameters.
9. The simulation experiment method according to claim 8, wherein the S2: the pre-test preparation step includes the following sub-steps:
s21: water injection and exhaust; injecting water into the two-phase flow measurement system (30) and the water supplementing system (40), exhausting, and then filling water into the reactor simulation body (10) and the steam simulation system (20);
s22: establishing a reactor simulator (10) vapor phase space; starting a steam simulation system (20), and communicating the steam simulation system (20) with a reactor simulator (10) when the deionized water is heated to a saturation temperature; heating power of a steam simulation system (20) is increased, saturated water is heated to generate saturated steam, and the liquid level in the reactor simulation body (10) reaches a preset liquid level;
s23: preheating a reactor simulator; and communicating the reactor simulation body (10) with a two-phase flow measurement system (30) to preheat the reactor simulation body (10) to a predetermined temperature.
10. The simulation experiment method according to claim 8, further comprising the steps of:
s5: and (3) reducing the temperature and the pressure, and gradually reducing the heating power of the steam simulation system (20) after test data are acquired.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311259329.5A CN117423485A (en) | 2023-09-26 | 2023-09-26 | Simulation experiment device and simulation experiment method for direct safety injection by-pass flow of reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311259329.5A CN117423485A (en) | 2023-09-26 | 2023-09-26 | Simulation experiment device and simulation experiment method for direct safety injection by-pass flow of reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN117423485A true CN117423485A (en) | 2024-01-19 |
Family
ID=89521863
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202311259329.5A Pending CN117423485A (en) | 2023-09-26 | 2023-09-26 | Simulation experiment device and simulation experiment method for direct safety injection by-pass flow of reactor |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN117423485A (en) |
-
2023
- 2023-09-26 CN CN202311259329.5A patent/CN117423485A/en active Pending
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Lorusso et al. | ALFRED Steam Generator Assessment: design and pre-test analysis of HERO experiment | |
| CN110783006B (en) | Degassing test device and method | |
| Lorusso et al. | Experimental analysis of stationary and transient scenarios of alfred steam generator bayonet tube in circe-hero facility | |
| Martelli et al. | Investigation of heat transfer in a steam generator bayonet tube for the development of PbLi technology for EU DEMO fusion reactor | |
| CN108231223A (en) | A kind of passive residual heat removal cycle performance test method | |
| Van Tichelen et al. | E-SCAPE: a scale facility for liquid-metal, pool-type reactor thermal hydraulic investigations | |
| Rozzia et al. | Experimental investigation on powder conductivity for the application to double wall heat exchanger (NACIE-UP) | |
| Narcisi et al. | Pool temperature stratification analysis in CIRCE-ICE facility with RELAP5-3D© model and comparison with experimental tests | |
| Zwijsen et al. | Multi-scale modelling of the CIRCE-HERO facility | |
| CN117423485A (en) | Simulation experiment device and simulation experiment method for direct safety injection by-pass flow of reactor | |
| Kauppinen et al. | Computer analyses on loop seal clearing experiment at PWR PACTEL | |
| Takeda et al. | Measurement of non-condensable gas in a PWR small-break LOCA simulation test with LSTF for OECD/NEA ROSA Project and RELAP5 post-test analysis | |
| Achilli et al. | SPES3 facility RELAP5 sensitivity analyses on the containment system for design review | |
| Bae et al. | Scaling methodology for a reduced-height reduced-pressure integral test facility to investigate direct vessel injection line break SBLOCA | |
| Lee et al. | Using an IIST SBLOCA experiment to assess RELAP5/MOD3. 2 | |
| Angelucci et al. | RELAP5 STH and Fluent CFD coupled calculations of a PLOHS+ LOF transient in the HLM experimental facility CIRCE | |
| Tarantino | Integral circulation experiment: thermal-hydraulic simulator of a LFR primary system | |
| Kim et al. | Experimental study of thermal mixing in flow mixing header assembly of SMART | |
| JPH0643282A (en) | Hydrothermal force mock-up test device for integral pressurized water reactor | |
| Tiberg | Simulation of IB-LOCA in TRACE: A semi-blind study of numerical simulations compared to the PKL test facility | |
| D'Auria et al. | Evaluation of the data base from the small break LOCA counterpart tests performed in LOBI, SPES, BETHSY and LSTF facilities | |
| Martelli et al. | Thermo-fluid dynamic analysis of HLM pool. Circe experiments | |
| Doda et al. | Numerical Analysis of EBR-II Shutdown Heat Removal Test-17 using 1D Plant Dynamic Analysis Code coupled with 3D CFD Code | |
| Gouat | Dimensioning the EVITA semi-open loop at BR2 for qualification of full size JHR fuel elements | |
| Lisowski et al. | Behavior of an air-cooled thermosiphon during a non-air gas ingress event |
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 |