CN210039653U - Compact pressurized water reactor primary loop system - Google Patents
Compact pressurized water reactor primary loop system Download PDFInfo
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- CN210039653U CN210039653U CN201920767188.0U CN201920767188U CN210039653U CN 210039653 U CN210039653 U CN 210039653U CN 201920767188 U CN201920767188 U CN 201920767188U CN 210039653 U CN210039653 U CN 210039653U
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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 utility model discloses a compact pressurized water reactor loop system, which comprises a pressure vessel, a steam generator, a main pump, a pressure stabilizer, a waste heat discharge system and a differential pressure liquid level meter, the pressure vessel is communicated with the steam generator through a first inner and outer sleeve structure, the pressure vessel is communicated with the main pump through a second inner and outer sleeve structure, the steam generator is communicated with the waste heat discharge system through a waste heat discharge pipe, the steam generator is communicated with the pressure stabilizer through a fluctuation pipe, the surge pipe is provided with a high pressure side measuring point at a position close to the steam generator, the surge pipe is provided with a vortex limiting pipe section positioned between the high pressure side measuring point and the steam generator, the differential pressure liquid level meter is respectively connected to the high-pressure side measuring point and the low-pressure side measuring point arranged on the voltage stabilizer through pressure guiding pipes. The utility model discloses can ensure waste heat discharge system's operational reliability, guarantee reactor core cooling function.
Description
Technical Field
The utility model relates to a pressurized water reactor technical field especially relates to a compact pressurized water reactor loop system.
Background
In the current large pressurized water reactor nuclear power project, for monitoring the water charge of a reactor coolant system in real time and ensuring the possibility of the reactor core submerging under any working condition, multi-section water level monitoring is generally adopted as a monitoring means in practical engineering, and diversified water level monitoring devices are respectively arranged at different stages of power operation, hot shutdown, cold shutdown and material changing overhaul of the reactor coolant system. During power operation, the water level in the cylinder of the pressure stabilizer is generally monitored, and the water level of the pressure container and the water level of the main pipeline are monitored during the filling and draining of a primary circuit. When a loop drains to the mid-plane water level (namely, the main pipeline water level), the residual heat removal system needs to strictly monitor the mid-plane water level because the residual heat removal system takes water from the main pipeline for cooling, and the residual heat removal system can reliably run.
However, in a new compact pressurized water reactor loop system (for example, chinese utility model patent No. ZL 201721417210.6), please refer to fig. 1, a main pipeline is not designed, but the main equipment is connected by an inner and outer sleeve structure 11, the system is a two-loop design, each loop includes a steam generator 12 and a main pump 13, the steam generator 12 is connected with a pressure vessel 14 by the inner and outer sleeve structure 11, and the main pump 13 is connected with the pressure vessel 14 by the inner and outer sleeve structure 11. The pressurizer 15 is connected to the primary side of the steam generator 12 through a surge pipe 16.
In this embodiment, the steam generator 12 is a once-through evaporator, and the heat transfer from the primary side to the secondary side is by means of spiral heat exchange tubes, where the primary side coolant runs out of the tubes and the secondary side water runs in the tubes. The piping connected to the primary side of the steam generator 12 includes a waste heat discharge nozzle, an upper charge nozzle, and a lower discharge nozzle (not shown) in addition to the surge pipes 16.
When primary circuit drainage is carried out, in order to ensure the normal operation of the waste heat discharge system 17, enough water volume margin above the waste heat discharge pipe nozzle is ensured, so that the residual heat discharge pump is prevented from generating cavitation erosion and even being incapable of taking enough water, and the water level of the primary circuit in the drainage process needs to be strictly monitored. A low water level signal may be set by monitoring the water level at the primary side of the steam generator 12, which signal triggers the waste heat removal system 17 to shut down during the drain phase when the water level is so low that reliable operation of the waste heat removal system is affected. As shown in fig. 1, a differential pressure liquid level meter 18 is arranged on the primary side of the steam generator 12, when the primary circuit is in the drainage stage, the reading of the differential pressure liquid level meter 18 reaches the low water level, the stop of the residual heat removal system 17 is triggered, the residual heat removal system 17 is ensured not to be damaged by cavitation, and after measures are taken to recover the water level, the residual heat removal system 17 is put into operation again.
This solution has a certain realism, but also has some problems. The caliber of the waste heat discharge nozzle is generally designed to be large, in the process of pumping by the waste heat discharge pump, the waste heat discharge nozzle on the primary side of the steam generator 12 can generate a vortex effect locally, and because the differential pressure liquid level meter 18 draws differential pressure by the high-level and low-level measuring points and converts the differential pressure into specific water level height, the effect can further cause the pressure at the high-pressure side measuring point of the differential pressure liquid level meter 18 on the primary side of the steam generator 12 to generate disturbance to a certain degree, so that false water level signals occur, the waste heat discharge pump can generate frequent pump tripping, the operation reliability of the waste heat discharge system 17 is influenced, and further the decay heat discharge is influenced.
SUMMERY OF THE UTILITY MODEL
An object of the utility model is to provide a compact pressurized water reactor loop system can ensure the operational reliability of waste heat discharge system, guarantees reactor core cooling function.
In order to achieve the aim, the utility model provides a compact pressurized water reactor loop system, which comprises a pressure vessel, a steam generator, a main pump, a voltage stabilizer, a waste heat discharge system and a differential pressure liquid level meter, the pressure vessel is communicated with the steam generator through a first inner and outer sleeve structure, the pressure vessel is communicated with the main pump through a second inner and outer sleeve structure, the steam generator is communicated with the waste heat discharge system through a waste heat discharge pipe, the steam generator is communicated with the pressure stabilizer through a fluctuation pipe, the surge pipe is provided with a high pressure side measuring point at a position close to the steam generator, the surge pipe is provided with a vortex limiting pipe section positioned between the high pressure side measuring point and the steam generator, the differential pressure liquid level meter is respectively connected to the high-pressure side measuring point and the low-pressure side measuring point arranged on the voltage stabilizer through pressure guiding pipes.
Preferably, the vortex limiting pipe section is an upright pipe section.
Preferably, the surge pipe further has a regulator connection pipe section and a horizontal pipe section connected between the vortex limiting pipe section and the regulator connection pipe section.
Preferably, the high pressure side measuring point is arranged at a position of the horizontal pipe section adjacent to the vortex limiting pipe section.
Preferably, an isolation valve is respectively arranged between the differential pressure liquid level meter and the pressure stabilizer and between the differential pressure liquid level meter and the steam generator.
Preferably, the pressurizer has a pressurizer vent valve located at an upper portion thereof, the steam generator has a generator vent valve located at an upper portion thereof, and the generator vent valve and the pressurizer vent valve are opened simultaneously.
Compared with the prior art, the utility model discloses set up the high pressure side measurement station on the surge pipe, the low pressure side measurement station sets up on the stabiliser, and be equipped with the vortex restriction pipeline section that is located between high pressure side measurement station and the steam generator at the surge pipe, thereby make the vortex phenomenon restricted the vortex restriction pipeline section basically, and the vortex phenomenon of high pressure side measurement point department obviously disappears, the disturbance that certain degree appears in the high pressure side measurement station pressure that has greatly weakened steam generator and has once inclining, make the water level signal who records more be close true, water level measurement's precision has been improved, make from this that the surplus pump can not appear frequent jump the pump, waste heat discharge system's operational reliability has been guaranteed. Furthermore, the utility model discloses can enlarge the monitoring range of a return circuit water level, and then reduce a return circuit water level measuring blind area. Furthermore, the utility model discloses still reduced the side measurement station on the steam generator, and then reduced the trompil quantity and the welding seam of steam generator's barrel, improved the integrality of equipment.
Drawings
FIG. 1 is a schematic diagram of a prior art compact pressurized water reactor loop system.
Fig. 2 is a schematic diagram of a loop system of a compact pressurized water reactor according to an embodiment of the present invention.
Fig. 3 is a schematic view of a surge tube in accordance with an embodiment of the present invention.
Detailed Description
In order to explain the contents, structural features, and objects and effects of the present invention in detail, the following description is given in conjunction with the embodiments and the accompanying drawings.
Referring to fig. 2 and 3, the present invention discloses a compact pressurized water reactor loop system, which comprises a pressure vessel 1, a steam generator 2, a main pump 3, the pressure stabilizer 4, the waste heat discharge system 5 and the differential pressure liquid level meter 6 are communicated with each other through a first inner and outer sleeve structure 7 between the pressure container 1 and the steam generator 2, the pressure container 1 and the main pump 3 are communicated through a second inner and outer sleeve structure 8, the steam generator 2 and the waste heat discharge system 5 are communicated through a waste heat discharge pipe 25, the steam generator 2 and the pressure stabilizer 4 are communicated through a fluctuation pipe 9, a high-pressure side measuring point 91 is arranged at one position, close to the steam generator 2, of the fluctuation pipe 9, the fluctuation pipe 9 is provided with a vortex limiting pipe section 92 between the high-pressure side measuring point 91 and the steam generator 2, and the differential pressure liquid level meter 6 is respectively connected to the high-pressure side measuring point 91 and a low-pressure side measuring point 41 arranged on.
The utility model discloses set up high pressure side measurement station 91 on surge pipe 9, low pressure side measurement station 41 sets up on stabiliser 4, and surge pipe 9 is equipped with the vortex restriction pipeline section 92 that is located between high pressure side measurement station 91 and the steam generator 2, thereby make the vortex phenomenon restricted at vortex restriction pipeline section 92 basically, and the vortex phenomenon of high pressure side measurement station 91 department obviously disappears, the disturbance that certain degree appears in high pressure side measurement station 91 pressure that has greatly weakened steam generator 2 and once inclines, make the water level signal who records more be close true, water level measurement's precision has been improved, make frequent jump pump can not appear in the excess discharge pump from this, the operational reliability of waste heat discharge system 5 has been guaranteed. Furthermore, the utility model discloses can enlarge the monitoring range of a return circuit water level, and then reduce a return circuit water level measuring blind area. Furthermore, the utility model discloses still reduced the side measurement station on the steam generator 2, and then reduced the trompil quantity and the welding seam of steam generator 2's barrel, improved the integrality of equipment.
It should be noted that the vortex limiting pipe section 92 in the present invention refers to a pipe section having a vortex limiting capability significantly higher than that of a horizontal pipe, and in the embodiment shown in fig. 3, it is a vertical pipe section, but it may also be an inclined pipe section having a higher upward inclination, or other pipe sections of various forms, as long as it can satisfy a shorter pipe section to perform a relatively larger vortex limiting function, so that the vortex phenomenon at the high pressure side measuring point 91 of the surge pipe 9 disposed near the steam generator 2 can be significantly eliminated, and the differential pressure liquid level meter 6 can obtain an accurate pressure value of the high pressure side measuring point 91. In some embodiments, surge duct 9 may be an inclined duct having a high upward inclination as a whole, and the bottom section of the inclined duct is a vortex limiting duct section 92, and high pressure side measuring point 91 is located on the upper side of and adjacent to the bottom section.
Referring to FIG. 3, in some embodiments, surge tube 9 also has a regulator connection tube 93 and a level tube 94 connected between vortex limiting tube 92 and regulator connection tube 93. The "horizontal pipe section 94" is not limited to an absolute horizontal position, and may be an approximate horizontal position.
In a preferred embodiment, a high pressure side test point 91 is provided at a location of the horizontal pipe section 94 adjacent to the vortex limiting pipe section 92; for example, in some embodiments, a vertical short pipe section may be connected between the upper end of the vertical pipe section and the horizontal pipe section, and the high pressure side measuring point 91 may be disposed at the short pipe section.
In some embodiments, an isolation valve 62 is provided between the differential pressure level gauge 6 and the pressure stabilizer 4 and the steam generator 2, respectively.
In some embodiments, the pressurizer 4 has a pressurizer vent valve 42 located at an upper portion thereof, and the steam generator 2 has a generator vent valve 21 located at an upper portion thereof, the generator vent valve 21 and the pressurizer vent valve 42 being opened or closed simultaneously. When the primary circuit is drained, the pressurizer vent valve 42 on the upper part of the pressurizer 4 needs to be opened to communicate the pressurizer 4 with the atmosphere so as to drain the water, and the generator vent valve 21 and the pressurizer vent valve 42 are opened simultaneously so as to communicate the primary side of the steam generator 2 with the atmosphere, so that the water level signal of the primary side of the steam generator 2 can be consistent with the water level signal in the surge pipe 9.
The above disclosure is only a preferred embodiment of the present invention, and the function is to facilitate the understanding and implementation of the present invention, which is not to be construed as limiting the scope of the present invention, and therefore, the present invention is not limited to the claims.
Claims (6)
1. A compact pressurized water reactor primary circuit system is characterized by comprising a pressure vessel, a steam generator, a main pump, a pressure stabilizer, a waste heat discharge system and a differential pressure liquid level meter, the pressure vessel is communicated with the steam generator through a first inner and outer sleeve structure, the pressure vessel is communicated with the main pump through a second inner and outer sleeve structure, the steam generator is communicated with the waste heat discharge system through a waste heat discharge pipe, the steam generator is communicated with the pressure stabilizer through a fluctuation pipe, the surge pipe is provided with a high pressure side measuring point at a position close to the steam generator, the surge pipe is provided with a vortex limiting pipe section positioned between the high pressure side measuring point and the steam generator, the differential pressure liquid level meter is respectively connected to the high-pressure side measuring point and the low-pressure side measuring point arranged on the voltage stabilizer through pressure guiding pipes.
2. The compact pressurized water reactor primary circuit system according to claim 1, wherein said vortex limiting pipe section is an upright pipe section.
3. The compact pressurized water reactor loop system according to claim 1 or 2, wherein the surge pipe further has a pressurizer connection section and a level pipe section connected between the vortex limiting section and the pressurizer connection section.
4. The compact pressurized water reactor primary circuit system according to claim 3, wherein said high pressure side test point is located at a position of said horizontal pipe section adjacent to said vortex limiting pipe section.
5. The compact PWR loop system of claim 1, wherein isolation valves are provided between the differential pressure level gauge and the pressurizer and the steam generator, respectively.
6. The compact pressurized water reactor loop system of claim 1 wherein said pressurizer has a pressurizer vent valve located at an upper portion thereof, and said steam generator has a generator vent valve located at an upper portion thereof, said generator vent valve and said pressurizer vent valve being opened simultaneously.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201920767188.0U CN210039653U (en) | 2019-05-24 | 2019-05-24 | Compact pressurized water reactor primary loop system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201920767188.0U CN210039653U (en) | 2019-05-24 | 2019-05-24 | Compact pressurized water reactor primary loop system |
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| Publication Number | Publication Date |
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| CN210039653U true CN210039653U (en) | 2020-02-07 |
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| CN201920767188.0U Active CN210039653U (en) | 2019-05-24 | 2019-05-24 | Compact pressurized water reactor primary loop system |
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| CN (1) | CN210039653U (en) |
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2019
- 2019-05-24 CN CN201920767188.0U patent/CN210039653U/en active Active
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