CN210722481U - External cooling three-dimensional test section of stagnant pressure vessel in melt reactor - Google Patents
External cooling three-dimensional test section of stagnant pressure vessel in melt reactor Download PDFInfo
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- CN210722481U CN210722481U CN201920805819.3U CN201920805819U CN210722481U CN 210722481 U CN210722481 U CN 210722481U CN 201920805819 U CN201920805819 U CN 201920805819U CN 210722481 U CN210722481 U CN 210722481U
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Abstract
The utility model discloses a three-dimensional test section of stagnant pressure vessel external cooling in melt heap, the test section setting is on the test bench, and the test bench includes: the device comprises a water tank, a heat exchanger, a vortex flowmeter, a transition section, a heating system, an ascending pipe, a descending pipe section, an outlet valve, an inlet valve, a heating system, a data acquisition and signal control system and a power supply control system; the test section comprises: the flow channel is in a hemispherical three-dimensional section shape, the end socket angle is 30 degrees, and 4 windows are uniformly arranged on two sides of the flow channel at intervals; the test section has 9 sections hot plates, and every section hot plate evenly distributed has the heating rod, controls heat flux density distribution through adjusting the heating rod power, and it has many thermocouples to distribute on every section hot plate to monitor the temperature distribution condition of whole heating section. The utility model discloses a scaling method carries out the scaling to the prototype size to adopted three-dimensional section model, shortened the time limit for a project and reduced under the condition of cost, can guarantee the accuracy of experiment again.
Description
Technical Field
The utility model relates to a nuclear power generation experiment technical field especially relates to three-dimensional test section of stagnant pressure vessel external cooling in melt heap.
Background
In the development process of nuclear power, nuclear safety is always a key concern of people. At present, more than 400 nuclear power stations in service exist in the world, and most of the nuclear power stations are built according to the second generation nuclear power technology. Although nuclear power plants have taken a series of measures to avoid serious accidents, serious accidents that exceed the design criteria may still occur under extreme conditions, such as the trie accident, the chernobeli accident and the fukushima accident. Once a serious accident happens, steam explosion, a large amount of radioactive substances are released and other serious consequences are likely to happen. The existing research shows that once a serious accident of reactor core fusion occurs in a nuclear power plant, the fused mass is cooled to ensure the integrity of a pressure vessel and a containment vessel, so that the release of radioactive substances can be greatly reduced, and the accident influence is reduced. Since then, a severe accident mitigation strategy for External Cooling (ERVC) of pressure vessels with In-Vessel Retention (IVR) In the melt heap has evolved internationally. The cooling water flows through a flow channel formed between the outer wall of the pressure container and the heat insulation layer, and the heat of the melt led out through the wall surface of the lower seal head of the pressure container is taken out, so that the boiling criticality on the surface of the lower seal head of the pressure container is prevented, and the integrity of the lower seal head is ensured. At present, IVR-ERVC becomes a core serious accident relieving measure in the third generation advanced nuclear power technology represented by AP1000 series. Similarly, in other advanced nuclear reactor types, the EVR-ERVC has wide application prospect.
Kymalaiinen et al studied Loviii power plants and systematically proposed IVR-ERVC serious accident mitigation measures and evaluation methods of external cooling effectiveness for the first time. The test uses a one-dimensional full-height loop to study the flow conditions of the fluid in the flow passage and CHF. It is concluded that ERVC can guarantee the implementation of IVR.
The most representative test is the ULPU series of tests conducted by the university of california, usa. The method aims to measure the critical heat flux density of the surface of the lower end socket and optimize the structure of the heat-insulating layer. The test uses full-scale test loops and test sections in slice configuration. The ULPU test project comprises five stages of tests, wherein the tests I, II and III aim at an AP600 pile type, the tests IV and V aim at an AP1000 pile type, and research tests are carried out on parameters such as the structure of a heat-insulating layer, an inlet and outlet structure and the like.
Also, the SBLB test was also conducted in korea for its advanced stack APR1400, using a scaling method, but scaling for a three-dimensional stage.
The CYBL test was performed by Sandia laboratories, usa using 1: a 1 ratio pressure vessel was experimentally investigated for the external cooling process boiling heat transfer and flow process.
As can be seen, most foreign researches adopt a model with a ratio of 1:1 to simulate the lower end socket, and even a slicing model is adopted, the lower end socket is simulated in a full size. Thus, the time consumption is large, and the engineering quantity is large.
In China, the Shanghai university of transportation also develops a 1:1 REPEC experiment, aims at a CPR1000 advanced high-power reactor type, and adopts a two-dimensional slice structure which simulates a pressure vessel in a full size. There are also some items that were calculated using software and tested using a tilted heated wall to mimic the heated wall.
In the prior art, IVR-ERVC correlation research is mostly carried out on a full-size model or a two-dimensional slice of a lower end socket, and as the prototype size is huge, the prototype slice is used for testing, so that the problems of long construction time, large cost and a lot of problems in the experimental process exist. Since the experimental section simulates the conditions of the reactor under extreme conditions and lacks the support of actual data, the reliability of the two-dimensional slice simulation result is not determined.
Therefore, the three-dimensional test section for external cooling of the pressure vessel retained in the melt reactor is expected to solve the problems of long experimental period, high cost and high accuracy in the prior art.
Disclosure of Invention
The utility model discloses a three-dimensional experimental section of stagnant pressure vessel external cooling in melt heap, its CHF's distribution law for studying the low head outer wall face under the inhomogeneous heat flux density explains the influence to the passive natural circulation characteristic such as circulation height, entry super-cooled rate, the utility model discloses a scaling method carries out the scaling to the prototype size to adopted three-dimensional section model, under the condition that has shortened the time limit for a project and reduce cost, can guarantee the accuracy of experiment again.
An externally cooled three-dimensional test section for a stagnant pressure vessel within a molten mass pile, said test section being disposed on a test rig, said test rig comprising: the device comprises a water tank, a heat exchanger, a vortex flowmeter, a transition area, a heating system, an ascending pipe, a descending pipe section, an outlet valve, an inlet valve, a heating system, a data acquisition and signal control system and a power control system, wherein a test section is arranged on the heating system, the upper end of the test section is connected with the ascending pipe section and is connected with the water tank through the outlet valve, the lower end of the test section is connected with the transition area and is connected with the water tank through the vortex flowmeter, the water tank is connected with the heat exchanger, the data acquisition and signal control system acquires signals at the outlet valve and the transition area, and the power control system controls the data acquisition and signal control system and the heating system;
the test section is characterized by comprising: the flow channel is of a hemispherical three-dimensional section type, the end socket angle is 30 degrees, and 4 windows are uniformly arranged on two sides of the flow channel at intervals so as to observe the flowing state of a medium in the flow channel, the generation of bubbles and the change in the flow channel when CHF occurs; the experimental section has 9 sections hot plates, and every section hot plate evenly distributed has the heating rod mounting hole, the heating rod mounting hole can be used to install the heating rod, controls heat flux density distribution through adjusting heating rod power, and it has many with the thermocouple mounting hole to distribute on every section hot plate, the thermocouple mounting hole can be used to install the thermocouple to monitor the temperature distribution condition of whole heating section.
Preferably, the heating rods of each section can be adjusted both largely and simultaneously for studying the influence of different heating conditions on the CHF and temperature distribution and the influence of the heating state of each zone on the external cooling.
Preferably, each section of heating plate is provided with 23 heating rod mounting holes; each section of the heating plate is distributed with 14 thermocouple mounting holes; the heating plate is made of pure copper.
Preferably, the thermocouple mounting holes on each section of heating plate are arranged in the following manner: the wall surface close to the flow channel is provided with 3 thermocouple mounting holes for detecting the distribution of the wall surface temperature and determining the position of a CHF (CHF) occurrence point; 3 thermocouple mounting holes are also arranged at corresponding radial positions; 4 thermocouple mounting holes are formed in the middle of the lower two rows of heating rods, longitudinal temperature distribution is monitored, and the heat flow direction of the heating plate is ensured to be mainly longitudinal; 2 thermocouple mounting holes are also formed in the symmetrical positions of the left side and the right side of the heating plate, and whether the transverse temperature distribution of the heating plate is uniform or not is observed; 1 thermocouple mounting hole is arranged on the uppermost surface of the heating plate, and the temperature of the area is measured and used as an overtemperature protection early warning signal; 1 thermocouple mounting hole is set at the joint of two sections of heating plates to confirm the continuity of heat flow.
Preferably, 2 light-emitting holes are formed in the bottom of the flow channel, a high-speed camera is used for shooting and recording, and the flowing state of the medium in the flow channel and the change of CHF are researched after graphic processing.
Preferably, the bottom of the flow channel is provided with a hole of 16 degrees as a cooling water inlet, and the hole is connected with the whole experiment bench through a flange to form a complete loop.
Preferably, a natural circulation loop is formed in the test process, under the state of full water, the fluid in the flow channel is heated, the density is reduced after the temperature is increased, the fluid enters the water tank at the upper part along the ascending pipe section due to the density difference, the low-temperature water in the water tank is replenished into the flow channel again through the descending pipe section, the descending pipe section is provided with a vortex flowmeter for monitoring the flow at any time, and the inlet valve and the outlet valve can adjust the flow.
The utility model discloses a three-dimensional test section of stagnant pressure vessel external cooling in melt reactor is directed at advanced high-power pressurized water reactor AP 1000's low head, adopts power-volume ratio analysis method and H2TS method to confirm the key parameter of experiment bench, guarantees that the important dimensionless criterion number of scaling model and reactor prototype is similar. The key problems mainly solved are as follows: CHF is the key to determining the effectiveness of IVR measures, and the distribution of CHF has obvious local characteristics for the structure that the heating surface of the outer wall surface of the lower end socket faces downwards and is provided with an inclined angle. And the degree of supercooling, vacuole share, circulation flow and circulation angle of the inlet fluid all influence its distribution characteristics, synthesize above factor, obtain the distribution law of CHF and establish reliable prediction model the utility model discloses the key scientific problem who plans to solve.
The utility model discloses a three-dimensional test section of melt in-pile detention pressure vessel external cooling can obtain the interior wall temperature of heating section under the different work condition, a series of time variation parameters such as test section pressure differential, and its influence to the experimental result is studied to the value that can change the constant parameter simultaneously. In the test process, CHF distribution rules, natural circulation characteristics and gas-liquid two-phase flow behaviors are mainly researched. The test section is mainly characterized in that for a specific reactor type, the lower end enclosure is scaled by a certain scaling means and then a three-dimensional slice is taken for testing, so that the feasibility of ERVC measures in severe accidents can be evaluated under the conditions of saving time and expenditure. The method can lay an experimental foundation for the design and the effectiveness verification of the IVR-ERVC system.
Drawings
FIG. 1 is a schematic view showing the connection relationship between the external cooling three-dimensional test sections of the pressure vessel for the molten material retained in the reactor.
FIG. 2 is a front view of an externally cooled three-dimensional test section of a stagnation pressure vessel in a melt stack according to the present invention.
FIG. 3 is a partial view of section A in a front view of a three-dimensional test section for external cooling of a stagnant pressure vessel within a melt stack according to the present invention.
Fig. 4 is a bottom view of an externally cooled three-dimensional test section of a stagnant pressure vessel within a melt stack of the present invention.
Detailed Description
In order to make the purpose, technical solution and advantages of the present invention clearer, the following will combine the drawings in the embodiments of the present invention to perform more detailed description on the technical solution in the embodiments of the present invention. In the drawings, the same or similar reference numerals denote the same or similar elements or elements having the same or similar functions throughout. The described embodiments are only some, but not all embodiments of the invention. The embodiments described below with reference to the drawings are exemplary and intended to be used for explaining the present invention, and should not be construed as limiting the present invention. Based on the embodiments in the present invention, all other embodiments obtained by a person skilled in the art without creative efforts belong to the protection scope of the present invention.
As shown in fig. 1-4, the size of the test rig is determined using a power-volume ratio analysis method to ensure that the scale model is similar to the number of important dimensionless criteria of the reactor prototype. And (3) taking a three-dimensional slice with the opening angle of 30 degrees of the lower end socket of the pressure container for analysis according to the contraction ratio of 1: 2. And heating the outer wall surface of the lower end enclosure model by using a heating rod embedded in the heating plate. In order to simulate the uneven distribution of heat flux density caused by the layering of the molten core in the lower end enclosure, the heating surface is divided into 9 regions along the inclination angle direction, and the heating power of the heating rod in each region is independently controlled and continuously adjustable.
The heating rods are uniformly distributed on the heating plate, and the power of the heating rods can be adjusted to control the distribution of heat flux density. The heating rods of each section can be adjusted either individually or simultaneously to study the effect of different heating conditions on CHF and temperature distribution, and the effect of heating conditions of each zone on external cooling.
Each heating plate is provided with 14 thermocouples to monitor the temperature distribution of the whole test section. The wall surface of the near flow channel is provided with 3 thermocouples for detecting the distribution of the wall surface temperature and determining the position of the CHF occurrence point. 3 thermocouples are distributed at corresponding radial positions, 4 thermocouples are distributed between the lower two rows of heating rods, longitudinal temperature distribution is monitored, the heat flow direction of the heating plate is ensured to be mainly longitudinal, 2 thermocouples are also arranged at symmetrical positions on the left side and the right side, and whether the transverse temperature distribution of the heating plate is uniform is observed. The uppermost surface of the heating plate is provided with 1 thermocouple, the surface is provided with a heat insulation layer, the highest temperature can occur, in order to ensure the integrity of the equipment, the thermocouple is used for detecting the temperature of the area, the temperature is used as an overtemperature protection early warning signal, and the heating is stopped when the temperature exceeds 600 ℃. The two adjacent sections of heating plates are separated, the heating plates are only kept in a connection state on the wall surface close to the flow channel, and the surface is used as an upper cover of the flow channel and is integrated with the flow channel made of stainless steel, so that the sealing performance of the flow channel is ensured. In addition, to ensure the continuity of heat flow between the sections, 1 thermocouple was placed at the junction of the two sections of heating plates to confirm the continuity of heat flow.
Two sides of the flow channel are uniformly provided with 4 windows to observe the flowing state of the medium in the flow channel, the generation of bubbles and the change in the flow channel when CHF occurs. And shooting and recording by using a high-speed camera, and researching the flowing state of the medium in the flow channel and the change of CHF after graphic processing. Because the high-speed camera needs to perform lighting during shooting and has higher requirements on a light source, a clear flow channel medium flowing video is shot for the convenience of meeting shooting lighting conditions so as to obtain better lighting conditions, and analysis and research are performed. Besides the two side windows of the flow channel, two polishing holes are also arranged at the bottom, which is shown in the attached figure 3 in detail.
The experimental study is carried out on the two-phase boiling heat transfer characteristic of the cooling water of the lower end socket, and the CHF distribution rule of the outer wall surface of the lower end socket is focused. And respectively adjusting the heat flux density of each heating plate of the test section to approximately simulate the heat flux density distribution of the lower end socket under serious accidents, and measuring the temperature of the wall surface of the heating surface and the temperature of the cooling water of the flow channel under the heat flux density to obtain the rule of the heat transfer coefficient. And integrally increasing the heating power until the temperature of the wall surface at a certain point rises, wherein the heat flux density at the moment is the critical heat flux density. And (3) obtaining a CHF distribution rule under the heating condition of the lower end socket three-dimensional slice curved surface by analyzing CHF values of different areas on the heating surface, and establishing a reliable CHF prediction model.
Observing and researching the two-phase flow of the cooling water of the lower end socket, researching the generation and flow conditions of bubbles in the flow channel in a high-speed camera shooting mode, researching important parameters such as the bubble share of the two-phase flow of the pipeline and the like, and the bubble condition of the heating wall surface when CHF occurs, and obtaining the generation rule of the two-phase flow in the pipeline under different heating conditions.
Finally, it should be pointed out that: the above embodiments are only used to illustrate the technical solution of the present invention, and not to limit it. Although the present invention has been described in detail with reference to the foregoing embodiments, it should be understood by those skilled in the art that: the technical solutions described in the foregoing embodiments may still be modified, or some technical features may be equivalently replaced; such modifications and substitutions do not depart from the spirit and scope of the present invention in its corresponding aspects.
Claims (7)
1. An externally cooled three-dimensional test section for a stagnant pressure vessel within a molten mass pile, said test section being disposed on a test rig, said test rig comprising: the device comprises a water tank, a heat exchanger, a vortex flowmeter, a transition area, a heating system, an ascending pipe, a descending pipe section, an outlet valve, an inlet valve, a heating system, a data acquisition and signal control system and a power control system, wherein a test section is arranged on the heating system, the upper end of the test section is connected with the ascending pipe section and is connected with the water tank through the outlet valve, the lower end of the test section is connected with the transition area and is connected with the water tank through the vortex flowmeter, the water tank is connected with the heat exchanger, the data acquisition and signal control system acquires signals at the outlet valve and the transition area, and the power control system controls the data acquisition and signal control system and the heating system;
the test section is characterized by comprising: the flow channel is of a hemispherical three-dimensional section type, and 4 windows are uniformly arranged on two sides of the flow channel at intervals so as to observe the flowing state of a medium in the flow channel, the generation of bubbles and the change in the flow channel when CHF occurs; the experimental section has 9 sections hot plates, and every section hot plate evenly distributed has the heating rod mounting hole, the heating rod mounting hole can be used to install the heating rod, controls heat flux density distribution through adjusting heating rod power, and it has many with the thermocouple mounting hole to distribute on every section hot plate, the thermocouple mounting hole can be used to install the thermocouple to monitor the temperature distribution condition of whole heating section.
2. The externally cooled three-dimensional test section of a stagnant pressure vessel within a melt stack according to claim 1, characterized in that: the heating rods of each section can be adjusted in a large heating way or simultaneously, and are used for researching the influence of different heating conditions on CHF and temperature distribution and the influence of the heating state of each area on external cooling.
3. The externally cooled three-dimensional test section of a stagnant pressure vessel within a melt stack according to claim 2, characterized in that: each section of heating plate is provided with 23 heating rod mounting holes; each section of the heating plate is distributed with 14 thermocouple mounting holes; the heating plate is made of pure copper.
4. The externally cooled three-dimensional test section of a stagnant pressure vessel within a melt stack according to claim 3, characterized in that: the thermocouple mounting hole on each section of heating plate is arranged in the following mode: the wall surface close to the flow channel is provided with 3 thermocouple mounting holes for detecting the distribution of the wall surface temperature and determining the position of a CHF (CHF) occurrence point; 3 thermocouple mounting holes are also arranged at corresponding radial positions; 4 thermocouple mounting holes are formed in the middle of the lower two rows of heating rods, longitudinal temperature distribution is monitored, and the heat flow direction of the heating plate is ensured to be mainly longitudinal; 2 thermocouple mounting holes are also formed in the symmetrical positions of the left side and the right side of the heating plate, and whether the transverse temperature distribution of the heating plate is uniform or not is observed; 1 thermocouple mounting hole is arranged on the uppermost surface of the heating plate, and the temperature of the area is measured and used as an overtemperature protection early warning signal; 1 thermocouple mounting hole is set at the joint of two sections of heating plates to confirm the continuity of heat flow.
5. The externally cooled three-dimensional test section of a stagnant pressure vessel within a melt stack according to claim 4, characterized in that: 2 light-emitting holes are formed in the bottom of the flow channel, a high-speed camera is used for shooting and recording, and the flowing state of the medium in the flow channel and the change of CHF (CHF) are researched after graphic processing.
6. The externally cooled three-dimensional test section of a stagnant pressure vessel within a melt stack according to claim 5, characterized in that: and a hole with 16 degrees is formed at the bottom of the runner and is used as a cooling water inlet, and the runner is connected with the test bed through a flange to form a complete loop.
7. The externally cooled three-dimensional test section of a stagnant pressure vessel within a melt stack according to claim 6, characterized in that: a natural circulation loop is formed in the test process, under the state of being filled with water, the fluid in the flow channel is heated, the density is reduced after the temperature is increased, the fluid enters the water tank at the upper part along the ascending pipe section due to the density difference, the low-temperature water in the water tank is replenished into the flow channel again through the descending pipe section, the descending pipe section is provided with a vortex flowmeter, the flow rate is monitored at any time, and the inlet valve and the outlet valve can adjust the flow rate.
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110097983A (en) * | 2019-05-30 | 2019-08-06 | 华北电力大学 | The cooling three dimensional taest section of stagnation pressure external container in a kind of fusant heap |
| CN113990537A (en) * | 2021-10-26 | 2022-01-28 | 中国核动力研究设计院 | Simulation body, simulation component and simulation method suitable for rotation body |
-
2019
- 2019-05-30 CN CN201920805819.3U patent/CN210722481U/en not_active Withdrawn - After Issue
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110097983A (en) * | 2019-05-30 | 2019-08-06 | 华北电力大学 | The cooling three dimensional taest section of stagnation pressure external container in a kind of fusant heap |
| CN110097983B (en) * | 2019-05-30 | 2023-12-08 | 华北电力大学 | External cooling three-dimensional test section of melt in-pile retention pressure vessel |
| CN113990537A (en) * | 2021-10-26 | 2022-01-28 | 中国核动力研究设计院 | Simulation body, simulation component and simulation method suitable for rotation body |
| CN113990537B (en) * | 2021-10-26 | 2023-10-20 | 中国核动力研究设计院 | Simulation body, simulation member and simulation method suitable for rotary forming body |
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