CN112927827A - Staggered jet type bubbler for nuclear reactor pressure suppression pool - Google Patents
Staggered jet type bubbler for nuclear reactor pressure suppression pool Download PDFInfo
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- CN112927827A CN112927827A CN202110038532.4A CN202110038532A CN112927827A CN 112927827 A CN112927827 A CN 112927827A CN 202110038532 A CN202110038532 A CN 202110038532A CN 112927827 A CN112927827 A CN 112927827A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/004—Pressure suppression
- G21C9/012—Pressure suppression by thermal accumulation or by steam condensation, e.g. ice condensers
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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
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Abstract
The invention provides a staggered jet bubbler of a nuclear reactor pressure-restraining pool, which comprises a pressure-relief steam pipeline, a main bubbler pipeline, a flow divider, a main bubbler pipeline flow guide hole and a flow divider flow guide hole, wherein the pressure-relief steam pipeline is provided with a plurality of pressure-relief steam holes; wherein, pressure release steam conduit links to each other with the bubbler trunk line, and the shunt links to each other with the bubbler trunk line is terminal, offers the water conservancy diversion hole that the multiseriate is parallel on the lateral wall of bubbler trunk line, and the shunt is cylindric hollow structure, and multiseriate shunt water conservancy diversion hole has been seted up along circumference to the up end of shunt. The steam jet flow from the flow divider greatly enhances the turbulence intensity of supercooled water, so that the average condensation heat exchange coefficient of the steam jet flow coming out from the side direction of the main pipeline is obviously improved, and the heat is released by the rapid condensation of the steam. Meanwhile, the steam jet flow mixed stirring in different directions can effectively reduce the thermal stratification phenomenon in the suppression pool, thereby reducing the potential damage of the uneven thermal stress to the suppression pool and improving the safety and reliability of the nuclear reactor.
Description
Technical Field
The invention belongs to the field of nuclear energy safety, and particularly relates to a staggered jet bubbler for a nuclear reactor pressure suppression pool.
Background
The suppression pool is a modern nuclear reactionImportant equipment in the reactor accident safety system, when the pressurized water reactor load reduces and leads to a loop pressure to rise, the steam on stabiliser upper portion can get into the bubbler through the relief valve, then discharges into the suppression pond with the form of efflux and condenses, reduces stabiliser pressure to maintain the stability of a loop pressure. In addition, when the loss of coolant accident happens to the boiling water reactor, the suppression pool also plays a crucial role in applying emergency cooling to a large amount of steam generated by the reactor core. Therefore, whether a pressurized water reactor or a boiling water reactor is adopted, the basic function of the suppression pool is to condense steam from a steam pipeline, and whether a large amount of steam can be rapidly cooled to become the primary task of the suppression pool or not. The heat exchange process of the steam and the supercooled water in the pressure suppression pool is called direct contact condensation, although the heat exchange coefficient can reach MW/m2K-order, but in an emergency, a large amount of steam is rushed into the water body of the suppression pool, and the volume of the suppression pool has to be increased by consuming a large amount of steam, so that the construction and operation and maintenance costs are increased. Published research shows that the thermal resistance of direct contact condensation of steam and supercooled water is on the water side, and the direct contact condensation heat exchange coefficient can be increased to 10MW/m by increasing the flow rate of the supercooled water through a pump2And the K-order remarkably improves the condensation rate of steam, but the cold water is difficult to accelerate in the suppression pool through a pump. In addition, near the bubbler, the temperature of the water body close to the jet flow core area is rapidly increased after latent heat of steam is absorbed, the hot water is floated on the surface and the cold water gradually sinks to the bottom layer due to small density of the hot water and large density of the cold water, the water body of the suppression pool has obvious thermal stratification along the vertical direction, public research shows that the temperature difference between the water body close to the jet flow core area and the water body far away from the core area can reach more than 50 ℃, and the structural safety of the suppression pool is seriously threatened due to uneven thermal stress caused by thermal stratification.
Disclosure of Invention
In order to solve the problems, the invention aims to provide a staggered jet bubbler of a nuclear reactor pressure suppression pool, which utilizes the acceleration effect of jet flow of a vertical direction spray hole on cold water to realize the enhancement of the jet flow condensation heat exchange process in the horizontal direction, improves the condensation rate of steam, and realizes the quick absorption of the pressure suppression pool on steam heat and the quick pressure regulation of a pipeline; on the other hand, large-scale longitudinal vortex can be formed in the suppression pool by utilizing staggered jet flows in different directions, so that the problem of thermal stratification of the suppression pool is solved.
In order to achieve the purpose, the invention adopts the technical scheme that:
a staggered jet bubbler for a nuclear reactor pressure suppression pool comprises a pressure relief steam pipeline, a bubbler main pipeline, a flow divider, a bubbler main pipeline flow guide hole and a flow divider flow guide hole; wherein, pressure release steam conduit links to each other with the bubbler trunk line, and the shunt links to each other with the bubbler trunk line is terminal, offers the water conservancy diversion hole that the multiseriate is parallel on the lateral wall of bubbler trunk line, and the shunt is cylindric hollow structure, and multiseriate shunt water conservancy diversion hole has been seted up along circumference to the up end of shunt.
A further development of the invention is that the diameter D of the flow guide opening is calculated by the following formula:
in the formula, msIs the single-hole steam flow, kappa is the adiabatic index, psIs the steam pressure, psIs the vapor density.
The invention is further improved in that the number N of the flow guide holes is calculated by the following formula:
in the formula, MsFor steam flow of the main pipeline of the bubbler, msIs a single orifice flow.
The invention is further improved in that the number of rows of the flow guide holes of the flow divider is the same as that of the flow guide holes of the main pipeline of the bubbler.
The invention is further improved in that the flow guide holes of the main bubbler pipeline are circumferentially arranged in a plurality of circles along the main bubbler pipeline, a plurality of rows are arranged along the height of the main bubbler pipeline, a plurality of circles are circumferentially arranged along the flow divider of the flow guide holes of the flow divider, and a plurality of rows are radially arranged along the flow divider. And at the same circumferential angle, the central point connecting line of the flow divider flow guide holes arranged along the radial direction of the flow divider is intersected with the central point connecting line of the bubbler main pipe flow guide holes arranged along the height of the bubbler main pipe.
The invention has the further improvement that the included angle alpha between the axis of the guide hole of the main pipeline of the bubbler and the main pipeline of the bubbler is less than 90 degrees, and the included angle beta between the axis of the guide hole of the splitter and the upper end surface of the splitter is less than 90 degrees.
The invention is further improved in that the guide hole of the main pipeline of the bubbler is a straight hole with equal section, the maximum flow speed of the outlet of the guide hole of the main pipeline of the bubbler is the sound speed, the guide hole of the flow divider is a through hole with a convergent-divergent section, and the maximum flow speed of the outlet of the guide hole of the flow divider is the supersonic speed.
The invention is further improved in that the diverter diversion holes are arranged in the range that the radius of the upper end surface of the diverter is less than <10D, and D is the diameter of the diversion hole.
The invention is further improved in that the number of the diversion holes of the flow divider
D is the diameter of the main pipeline flow guide hole of the bubbler, DF is the diameter of the inlet and outlet of the flow divider flow guide hole, D is the center distance between adjacent flow divider flow guide holes, alpha is the included angle between the axis of the main pipeline flow guide hole of the bubbler and the main pipeline of the bubbler, and beta is the included angle between the axis of the flow divider flow guide hole and the upper end face of the flow divider.
Compared with the prior art, the invention has the following beneficial effects:
the invention provides a staggered jet type bubbler of a nuclear reactor pressure-restraining pool, which is characterized in that a plurality of rows of parallel guide holes are formed in the side wall of a main pipeline of the bubbler, and a plurality of rows of splitter guide holes are formed in the upper end surface of a splitter along the circumferential direction, so that steam can form staggered jet flows in the horizontal direction and the vertical direction in the pressure-restraining pool after coming out of the bubbler. The flow velocity of the supercooled water is increased to dozens of meters per second by utilizing the steam jet condensation in the vertical direction, and the turbulence intensity of the water side condensed by the steam jet in the horizontal direction is improved, so that the average heat exchange coefficient in the steam jet condensation process in the horizontal direction is obviously improved, the steam condensation rate of a bubbler is favorably improved, and the design volume and the construction cost of a suppression pool are reduced; the invention forms a large-scale longitudinal vortex in the suppression pool by steam staggered jet flow in two directions, and forms violent stirring in the vertical direction, thereby overcoming the defect of insufficient stirring of the traditional single-phase jet bubbler, effectively eliminating the phenomenon of thermal stratification in the suppression pool, reducing the uneven thermal stress of the wall surface of the suppression pool, and improving the safety and reliability of the nuclear reactor.
Drawings
Fig. 1 is a front view of a staggered jet bubbler for a nuclear reactor suppression pool in accordance with the present invention.
Fig. 2 is a top view of a staggered jet bubbler for a nuclear reactor suppression pool in accordance with the present invention.
Fig. 3 shows the setting angle of the guide holes of the staggered jet bubbler in the nuclear reactor pressure-restraining pool according to the present invention.
Fig. 4 shows the shape of the guide holes of the staggered jet bubbler for the suppression pool of the nuclear reactor according to the present invention.
Fig. 5 shows the operating principle of the staggered jet bubbler for the suppression pool of the nuclear reactor according to the present invention.
FIG. 6 is a liquid phase velocity distribution cloud chart of the direct contact condensation process of sonic steam jet and supercooled water obtained by three-dimensional numerical simulation.
Fig. 7 is a radial velocity distribution diagram of direct contact condensation of high-speed steam jet and supercooled water, which is measured by experimental research in the published technical documents.
Wherein: 1 is a pressure relief steam pipeline; 2 is a main bubbler pipeline; 3 is a flow divider; 4, a main pipeline flow guide hole of the bubbler; 5 is a flow guide hole of the flow divider, and 6 is a suppression pool.
Detailed Description
The invention will be further described with reference to the accompanying drawings.
Referring to fig. 1, the staggered jet bubbler for a nuclear reactor pressure-restraining pool provided by the invention is arranged in a nuclear reactor pressure-restraining pool 6 and comprises a pressure-relief steam pipeline 1, a main bubbler pipeline 2, a flow divider 3, a main bubbler pipeline flow guide hole 4 and a flow divider flow guide hole 5. Pressure release steam conduit 1 links to each other with bubbler trunk line 2, and shunt 3 links to each other with 2 ends of bubbler trunk line, and the parallel water conservancy diversion hole 4 of multiseriate is seted up to the side of bubbler trunk line 2, and the diameter D of water conservancy diversion hole 4 is calculated by the following formula and is obtained:
in the formula, msIs the single-hole steam flow, kappa is the adiabatic index, psIs the steam pressure, psIs the vapor density.
The pressure relief steam pipeline 1 is horizontally arranged, and the main pipeline 2 of the bubbler is vertically arranged. The number N of the flow guide holes 4 can be determined by the steam flow M of the main pipeline of the bubblersWith a single orifice flow msCalculated to obtain, i.e. N ═ Ms/msThe flow divider 3 is of a cylindrical hollow structure, a plurality of columns of flow divider flow guide holes 5 are formed in the upper end face connected with the main pipeline 2 of the bubbler along the circumferential direction, the columns of the flow divider flow guide holes 5 are the same as the flow guide holes 4 of the main pipeline of the bubbler, and the flow guide holes are not formed in the lower end face of the flow divider 3.
Referring to fig. 2 and 3, at the same circumferential position, the connection line of the central points of the radial splitter diversion holes 5 is intersected with the connection line of the central points of the axial bubbler main pipeline diversion holes 4, the included angle alpha between the axis of the bubbler main pipeline diversion hole 4 and the bubbler main pipeline 2 is less than 90 degrees, the included angle beta between the axis of the splitter diversion hole 5 and the upper end surface of the splitter 3 is less than 90 degrees, large-scale longitudinal vortexes can be formed at the lower reaches of the jet holes, and the liquid mixing of different temperatures in the vertical direction of the suppression pool can be promoted.
Referring to a sectional view of the bubbler main pipe flow guide hole 4 in fig. 4, (a) is a sectional view of the bubbler main pipe flow guide hole 4, the structure of the bubbler main pipe flow guide hole 4 is a straight-through hole with a uniform cross section, the maximum flow rate of steam at the outlet of the bubbler main pipe flow guide hole 4 is a sound velocity, fig. 4 (b) is a sectional view of the flow divider flow guide hole 5, the structure of the flow divider flow guide hole 5 is a through hole with a convergent-divergent cross section, and the flow rate of steam at the outlet of the flow divider flow guide hole 5 can reach a supersonic velocity, so that a strong acceleration effect is generated on liquid.
Referring to fig. 3, the diameter of the throat of the diverter diversion hole 5 is equal to the diameter D of the bubbler main pipeline diversion hole 4, the inlet and outlet diameters of the diverter diversion hole 5 are DF, and DF is greater than D. When steam enters super-cooled water through a hole or a nozzle to be condensed by accelerating jet flow, a jet flow core area (steam plume) is formed at an outlet of a jet hole, the dimensionless penetration length L/D of the steam plume in the prior art is 1-10, and L is the penetration length of the steam plume. The jet flow of the splitter diversion hole 5 is mainly used for strengthening the heat exchange of the jet flow core area of the main pipeline diversion hole 4 of the bubbler, so that the splitter diversion hole 5 is only required to be arranged in the range that the radius of the upper end surface of the splitter 3 is less than 10D. Assuming that the distance between the centers of two adjacent diverter guide holes 5 is d, the number n of diverter guide holes 5 can be calculated by the following formula:
in the formula, D is the diameter of bubbler trunk line water conservancy diversion hole 4, DF is the access & exit diameter of shunt water conservancy diversion hole 5, D is the interaxial distance of adjacent shunt water conservancy diversion hole 5, alpha is the contained angle of the axis of bubbler trunk line water conservancy diversion hole 4 and bubbler trunk line 2, beta is the contained angle of shunt water conservancy diversion hole 5 axis and 3 up ends of shunt.
Referring to fig. 5, when the staggered jet bubbler of the nuclear reactor pressure-restraining pool provided by the invention normally works, most steam is discharged into the pressure-restraining pool 6 through the main pipeline flow guide hole 4 of the bubbler to release latent heat to become hot water, and a small part of steam is expanded and accelerated through the flow divider flow guide hole 5 to form upward supersonic jet, so that the flow velocity of the supercooled water is greatly improved while heat exchange is carried out with the supercooled water, thereby obviously enhancing the direct contact condensation heat exchange of the steam and the liquid at the outlet of the main pipeline flow guide hole 4 of the bubbler, and promoting the rapid absorption of the pressure-restraining pool to the steam heat; on the other hand, the staggered jet flow can form a longitudinal large vortex in the suppression pool, promote the mixing of supercooled water with different heights in the vertical direction, effectively avoid the occurrence of a thermal stratification phenomenon, prevent the potential damage of thermal stress to the wall surface structure of the suppression pool, and improve the safety and reliability of the nuclear reactor.
Referring to FIG. 6, in the present invention, the steam mass flow rate is 527kg/m at the nozzle hole outlet diameter of 8mm2s, under the conditions that the Mach number of a steam outlet is 1 and the water temperature is 40 ℃, the direct contact condensation of sonic steam and supercooled water is obtained by adopting three-dimensional numerical simulationCloud diagram of liquid phase velocity profile of the process, and the technical document disclosed in FIG. 7 (Wu XZ, Yan JJ, Li WJ, et al]The results of experimental measurements reported by Nuclear Engineering and Design,2010,240(10):3259-3266.) were close (the measurement conditions were: the diameter of the outlet of the spray hole is 8mm, and the steam mass flow rate is 583kg/m2s, the Mach number of the steam outlet is unknown, the water temperature is 30 ℃), and the accuracy of the numerical simulation result of the method can be verified. After the sonic steam is condensed, the velocity of the supercooled water can be increased to more than 20m/s, the supersonic steam jet is condensed to obtain higher liquid phase velocity, and the invention can be supported by utilizing the jet flow in the vertical direction to increase the liquid phase velocity so as to strengthen the assumption of the condensation process of the steam jet flow in the horizontal direction.
Claims (9)
1. A staggered jet-type bubbler for a nuclear reactor pressure suppression pool is characterized by comprising a pressure relief steam pipeline (1), a bubbler main pipeline (2), a flow divider (3), a bubbler main pipeline guide hole (4) and a flow divider guide hole (5); wherein, pressure release steam conduit (1) links to each other with bubbler trunk line (2), and shunt (3) link to each other with bubbler trunk line (2) end, offer tympanic bulla trunk line water conservancy diversion hole (4) that the multiseriate is parallel on the lateral wall of bubbler trunk line (2), and shunt (3) are cylindric hollow structure, and multiseriate shunt water conservancy diversion hole (5) have been seted up along circumference to the up end of shunt (3).
2. A staggered jet bubbler for a nuclear reactor suppression pool according to claim 1, wherein the diameter D of the bubbler main conduit guiding holes (4) is calculated by the following formula:
in the formula, msIs the single-hole steam flow, kappa is the adiabatic index, psIs the steam pressure, psIs the vapor density.
3. A staggered jet bubbler for a nuclear reactor suppression pool according to claim 1, wherein the number N of bubbler main conduit guiding holes (4) is calculated by:
in the formula, MsFor steam flow of the main pipeline of the bubbler, msIs a single orifice flow.
4. A nuclear reactor hold-down tank interdigitated jet bubbler as claimed in claim 1, wherein the number of rows of diverter deflector holes (5) is the same as the number of rows of bubbler main conduit deflector holes (4).
5. The staggered jet bubbler for a nuclear reactor suppression pool according to claim 1 or 4, wherein the bubbler main pipe diversion holes (4) are arranged in a plurality of circles along the circumference of the bubbler main pipe (2), in a plurality of rows along the height of the bubbler main pipe (2), in a plurality of circles along the circumference of the splitter (3) and in a plurality of rows along the radial direction of the splitter (3) in the splitter diversion holes (5). At the same circumferential angle, the central point connecting line of the flow divider diversion holes (5) which are radially arranged along the flow divider (3) is intersected with the central point connecting line of the bubbler main pipeline diversion holes (4) which are highly arranged along the bubbler main pipeline (2).
6. The staggered jet bubbler of a nuclear reactor suppression pool according to claim 5, wherein the angle α between the axis of the bubbler main pipe diversion hole (4) and the bubbler main pipe (2) is less than 90 °, and the angle β between the axis of the splitter diversion hole (5) and the upper end face of the splitter (3) is less than 90 °.
7. The staggered jet bubbler for a nuclear reactor suppression pool according to claim 1, wherein the bubbler main pipe flow guide holes (4) are straight holes with uniform cross-section, the maximum flow velocity at the outlet of the bubbler main pipe flow guide holes (4) is sonic velocity, the splitter flow guide holes (5) are through holes with convergent-divergent cross-section, and the maximum flow velocity at the outlet of the splitter flow guide holes (5) is supersonic velocity.
8. The staggered jet bubbler for a nuclear reactor suppression pool according to claim 7, wherein splitter guide holes (5) are formed in the splitter (3) within a radius of the upper end surface of less than <10D, where D is the diameter of the guide holes (4).
9. A nuclear reactor depression pool staggered jet bubbler as claimed in claim 1 wherein the number of diverter deflector holes (5) is calculated by the formula:
d is the diameter of the main pipeline flow guide hole (4) of the bubbler, DF is the diameter of the inlet and outlet of the flow divider flow guide hole (5), D is the center distance between adjacent flow divider flow guide holes (5), alpha is the included angle between the axis of the flow divider flow guide hole (4) and the main pipeline (2) of the bubbler, and beta is the included angle between the axis of the flow divider flow guide hole (5) and the upper end face of the flow divider (3).
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114388154A (en) * | 2021-11-26 | 2022-04-22 | 中国船舶重工集团公司第七一九研究所 | Jet mixing enhanced passive suppression system |
Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4022655A (en) * | 1973-12-12 | 1977-05-10 | Commissariat A L'energie Atomique | Device for limiting accidental pressure overloads in a nuclear reactor confinement structure |
| EP0353596A2 (en) * | 1988-08-04 | 1990-02-07 | Günter Schüssler | Aerated bath with controlled bubbling activity |
| CN204017755U (en) * | 2014-08-12 | 2014-12-17 | 象山智欧机械有限公司 | A kind of airflow stirring blender |
| CN108364700A (en) * | 2018-02-13 | 2018-08-03 | 中国核动力研究设计院 | A kind of bubblers combined using more bubbling arms and bubbling ring |
| CN111667932A (en) * | 2020-06-22 | 2020-09-15 | 中国核动力研究设计院 | Immersion type externally-tangent rotational flow type bubbler structure |
| CN111863292A (en) * | 2020-07-16 | 2020-10-30 | 上海交通大学 | Bubbler optimization method for reducing condensation impact effect |
| CN111991830A (en) * | 2020-08-25 | 2020-11-27 | 上海核工程研究设计院有限公司 | Pressure relief bubbling device and method for nuclear power station |
-
2021
- 2021-01-12 CN CN202110038532.4A patent/CN112927827B/en active Active
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4022655A (en) * | 1973-12-12 | 1977-05-10 | Commissariat A L'energie Atomique | Device for limiting accidental pressure overloads in a nuclear reactor confinement structure |
| EP0353596A2 (en) * | 1988-08-04 | 1990-02-07 | Günter Schüssler | Aerated bath with controlled bubbling activity |
| CN204017755U (en) * | 2014-08-12 | 2014-12-17 | 象山智欧机械有限公司 | A kind of airflow stirring blender |
| CN108364700A (en) * | 2018-02-13 | 2018-08-03 | 中国核动力研究设计院 | A kind of bubblers combined using more bubbling arms and bubbling ring |
| CN111667932A (en) * | 2020-06-22 | 2020-09-15 | 中国核动力研究设计院 | Immersion type externally-tangent rotational flow type bubbler structure |
| CN111863292A (en) * | 2020-07-16 | 2020-10-30 | 上海交通大学 | Bubbler optimization method for reducing condensation impact effect |
| CN111991830A (en) * | 2020-08-25 | 2020-11-27 | 上海核工程研究设计院有限公司 | Pressure relief bubbling device and method for nuclear power station |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114388154A (en) * | 2021-11-26 | 2022-04-22 | 中国船舶重工集团公司第七一九研究所 | Jet mixing enhanced passive suppression system |
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