CN113421662A - Natural circulation cooling method under failure of liquid level indication of pressure vessel of nuclear power plant - Google Patents
Natural circulation cooling method under failure of liquid level indication of pressure vessel of nuclear power plant Download PDFInfo
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- CN113421662A CN113421662A CN202110676887.6A CN202110676887A CN113421662A CN 113421662 A CN113421662 A CN 113421662A CN 202110676887 A CN202110676887 A CN 202110676887A CN 113421662 A CN113421662 A CN 113421662A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/08—Regulation of any parameters in the plant
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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
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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 discloses a natural circulation cooling method under the condition of liquid level indication failure of a pressure container of a nuclear power plant, which comprises the following steps: starting a cooling fan of a control rod driving mechanism, and boronating a main system to the boron concentration of a cooling reactor; cooling and depressurizing the main system to make the temperature of the hot section of the main system lower than the first temperature and the pressure of the main system lower than the first pressure; cooling and depressurizing the main system to reduce the temperature of the hot section of the main system to a second temperature and reduce the pressure of the main system to a second pressure; cooling the main system to reduce the temperature of the hot section to a set temperature; putting in a waste heat discharge system, and continuously cooling the main system to a cold shutdown working condition; by adopting a step-type main system cooling and pressure reducing method and strictly setting limiting conditions for limiting cooling and pressure reducing rates and the like, the flash evaporation and steam production of the upper end enclosure are avoided; the steam generation condition of the upper end enclosure in the natural circulation cooling process is judged by monitoring and controlling the water level of the pressure stabilizer, and possible steam is eliminated.
Description
Technical Field
The invention relates to the field of assembly type buildings, in particular to a natural circulation cooling method under the condition of liquid level indication failure of a pressure container of a nuclear power plant.
Background
After the accident of 'Hualongyi' pressurized water reactor nuclear power plant which is not triggered or does not need to trigger safety injection occurs, the reactor is automatically and emergently stopped, and an operator needs to control and relieve the accident consequence according to the emergency accident regulation. If the initial cause of the accident can not be repaired in the hot state of the reactor, the reactor needs to be cooled to a cold shutdown state for fault treatment. In this process, if the main system main pump, which is shut down, cannot be started again, the reactor main system needs to establish a natural circulation to cool the core.
During the natural circulation operation of the main system, steam can be generated in the upper head area of the reactor pressure vessel due to the flash evaporation of fluid, and the liquid level of the pressure vessel is reduced.
Under the usual condition, an operator can monitor the liquid level change of the pressure container by using a pressure container water level indicating system, judge whether the upper seal head generates steam or not and take a treatment measure for eliminating the steam generation in time. However, when the water level indicating system of the pressure container fails, the steam generation condition and the water level change of the upper end enclosure of the pressure container cannot be judged and identified in time, and continuous flash evaporation of fluid of the upper end enclosure can cause a large amount of steam to be accumulated, so that the liquid level in the pressure container is rapidly reduced and is lower than the upper surface of the heat pipe section, natural circulation of a main system is stopped, waste heat of a reactor core is discharged and fails, and the safety of the reactor is seriously threatened.
Disclosure of Invention
The invention aims to solve the problems and provide a natural circulation cooling method under the condition of failure of liquid level indication of a pressure vessel of a nuclear power plant.
A natural circulation cooling method for a nuclear power plant pressure vessel under the condition of liquid level indication failure comprises the following steps:
s1, starting a cooling fan of the control rod driving mechanism, and boronizing the main system to the boron concentration of the cooling reactor;
s2, cooling and depressurizing the main system to enable the temperature of the hot section of the main system to be lower than the first temperature and the pressure of the main system to be reduced to the first pressure;
s3, locking safety injection signals, maintaining the stability of the parameter cooling process of the system, and ensuring that the temperature of a thermocouple at the outlet of the reactor core is reduced, the temperature of a hot section of a main system is reduced, and the supercooling degree of the outlet of the reactor core is increased;
s4, adjusting the upper charging flow and the lower discharging flow of the voltage stabilizer, and controlling the water level of the voltage stabilizer between a first range and a second range;
s5, cooling and depressurizing the main system to reduce the temperature of the hot section of the main system to a second temperature and reduce the pressure of the main system to a second pressure;
s6, cooling the main system to reduce the temperature of the hot section to a set temperature;
s7, adjusting the voltage stabilizer to make the charging flow rate equal to the discharging flow rate;
s8, reducing the pressure of the main system;
s9, monitoring the water level of the voltage stabilizer, and jumping to the step S10 when the water level of the voltage stabilizer is larger than a third range; when the water level of the voltage stabilizer is smaller than the third range, the step S11 is skipped to;
s10, putting an electric heater into the main system to boost the pressure of the main system and increase the pressure, and jumping to the step S8;
s11, obtaining a main system pressure, and if the main system pressure is higher than the set pressure, jumping to the step S8;
and S12, putting in a waste heat discharge system, and continuously cooling the main system to the cold shutdown working condition.
Further, steps S6-S11 are repeated so that the main system hot leg temperature equals the final temperature and the main system pressure equals the final pressure.
Specifically, the steps S6 to S11 are repeated, specifically including the following steps:
a1, cooling the main system to reduce the temperature of the hot section to a third temperature;
a2, adjusting the voltage stabilizer to make the upper charging flow equal to the lower discharging flow;
a3, reducing the pressure of the main system;
a4, monitoring the water level of the voltage stabilizer, and jumping to the step A5 when the water level of the voltage stabilizer is larger than a third range; when the water level of the voltage stabilizer is smaller than the third range, the step A6 is skipped to;
a5, putting an electric heater into the main system to boost the pressure of the main system and increase the pressure, and jumping to the step A3;
a6, acquiring a main system pressure, and jumping to the step A3 if the main system pressure is higher than the third pressure; if the main system pressure is equal to the third pressure, then go to step A7;
a7, cooling the main system to reduce the temperature of the hot section to a fourth temperature;
a8, adjusting the voltage stabilizer to make the upper charging flow equal to the lower discharging flow;
a9, reducing the pressure of the main system;
a10, monitoring the water level of the voltage stabilizer, and jumping to the step A11 when the water level of the voltage stabilizer is larger than a third range; when the water level of the voltage stabilizer is smaller than the third range, the step A12 is skipped to;
a11, putting an electric heater into the main system to boost the pressure of the main system and increase the pressure, and jumping to the step A9;
a12, obtaining a main system pressure, and jumping to the step A9 if the main system pressure is higher than the fourth pressure; if the main system pressure is equal to the fourth pressure, go to step A13;
a13, cooling the main system to reduce the temperature of the hot section to the final temperature;
a14, adjusting the voltage stabilizer to make the upper charging flow equal to the lower discharging flow;
a15, reducing the pressure of the main system;
a16, monitoring the water level of the voltage stabilizer, and jumping to the step A17 when the water level of the voltage stabilizer is larger than a third range; when the water level of the voltage stabilizer is smaller than the third range, the step A18 is skipped to;
a17, putting an electric heater into the main system to boost the pressure of the main system and increase the pressure, and jumping to the step A15;
a18, obtaining a main system pressure, and if the main system pressure is higher than the final pressure, jumping to the step A15; if the main system pressure is equal to the final pressure, go to step A19;
and A19, putting in a waste heat discharge system, and continuously cooling the main system to the cold shutdown working condition.
Preferably, in the cooling process of step S2, the main system cooling rate is maintained to be less than the basic rate, the voltage regulator water level is maintained at the zero load water level, and the main system temperature and pressure are maintained within the cooling and pressure reduction curve limit values;
in the cooling process of step S5, maintaining the main system pressure at the first pressure, maintaining the main system cooling rate at a rate less than the first rate, and maintaining the main system temperature and pressure within the limits of the cooling and depressurizing curve;
preferably, during the temperature reduction process of step a1, the main system pressure is maintained at the second pressure, the main system temperature reduction rate is maintained to be less than the second rate, and the main system temperature and pressure are maintained within the temperature reduction and pressure reduction curve limit values;
preferably, during the temperature reduction process in step a7, the main system pressure is maintained at the third pressure, the main system temperature reduction rate is maintained to be less than the third rate, and the main system temperature and pressure are maintained within the temperature reduction and pressure reduction curve limit values;
preferably, during the cool down of step a13, the main system pressure is maintained at the fourth pressure, the main system cool down rate is maintained less than the fourth rate, and the main system temperature and pressure are maintained within the cool down depressurization curve limits.
Specifically, after step a6 is completed, step a7 is performed after the safety injection tank needs to be isolated.
As an example, the first temperature is 284 ℃, the second temperature is 258 ℃, the third temperature is 230 ℃, the fourth temperature is 202 ℃, the final temperature is 177 ℃, the first pressure is 13.56mpa (a), the second pressure is 11.1mpa (a), the third pressure is 7.0mpa (a), the fourth pressure is 4.14mpa (a), the final pressure is 2.7mpa (a), the incremental pressure is 0.7mpa (a), the first range is 12% range, the second range is 22% range, the third range is 86% range, the base rate is 14 ℃/h, the first rate is 28 ℃/h, the second rate is 28 ℃/h, the third rate is 56 ℃/h, and the fourth rate is 56 ℃/h.
A method of cooling a pressurized water reactor nuclear power plant comprising the steps of:
triggering reactor shutdown in case of a reactor accident;
step two, if the main system main pump fails to start, natural circulation cooling is executed;
and step three, if the liquid level indication of the pressure vessel fails, executing the natural circulation cooling method under the condition that the liquid level indication of the pressure vessel of the nuclear power plant fails.
Compared with the prior art, the invention avoids the flash evaporation and steam production of the upper end enclosure by adopting a step-type main system cooling and pressure reduction method and strictly setting limiting conditions of limiting cooling and pressure reduction rates and the like; the steam generation condition of the upper end enclosure in the natural circulation cooling process is judged by monitoring and controlling the water level of the pressure stabilizer, and possible steam is eliminated.
Drawings
The accompanying drawings, which are included to provide a further understanding of the invention and are incorporated in and constitute a part of this specification, illustrate exemplary embodiments of the invention and together with the description serve to explain the principles of the invention.
Fig. 1 is a schematic flow diagram of a method for cooling a pressurized water reactor nuclear power plant according to the present invention.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention will be further described in detail with reference to the accompanying drawings and embodiments. It is to be understood that the specific embodiments described herein are for purposes of illustration only and are not to be construed as limitations of the invention.
It should be noted that, for convenience of description, only the portions related to the present invention are shown in the drawings.
In the present invention, the embodiments and features of the embodiments may be combined with each other without conflict. The present invention will be described in detail below with reference to the accompanying drawings in conjunction with embodiments.
A method of cooling a pressurized water reactor nuclear power plant comprising the steps of:
triggering reactor shutdown in case of a reactor accident;
step two, if the main system main pump fails to start, natural circulation cooling is executed;
and step three, if the liquid level indication of the pressure vessel fails, executing the natural circulation cooling method under the condition that the liquid level indication of the pressure vessel of the nuclear power plant fails.
If an accident occurs in a pressurized water reactor nuclear power plant and the emergency shutdown condition occurs, the accident condition needs to be analyzed.
The main system main pump, i.e., the nuclear main pump, is a pump for driving coolant to circulate in an RCP (reactor coolant system) system in the nuclear island primary circuit system. The main pump is positioned at the heart of the nuclear island and used for pumping hot water into the evaporator to convert heat energy, the main pump continuously transfers the heat generated in the reactor core to the secondary side (two loops) of the steam generator to supply water, which is the key for controlling water circulation in nuclear power operation, and each steam generator is provided with one main pump.
After a reactor accident triggers shutdown, a main system main pump needs to be started in time to cool a main system, and if the main system main pump is started normally, the main system is cooled through an RCP (reactor coolant) system.
If the main system main pump fails to start, the reactor needs to be cooled by means of natural circulation.
In the process of executing natural circulation cooling, the liquid level change of the pressure container needs to be monitored through a pressure container water level indicating system to judge whether the upper end enclosure generates steam or not.
Therefore, before natural circulation cooling is executed, the pressure container water level indicating system is detected, and if the pressure container water level indicating system can work normally, natural circulation cooling is performed according to a conventional process.
If the pressure vessel water level indication system is not working properly, it needs to be cooled by the method provided in this embodiment.
Example one
A natural circulation cooling method for a nuclear power plant pressure vessel under the condition of liquid level indication failure comprises the following steps:
s1, starting a cooling fan of the control rod driving mechanism, and boronizing the main system to the boron concentration of the cooling reactor;
and determining that the main system reaches a cold stop reactor boron concentration value through sampling analysis, and setting the supply control of the reactor boron and water supply system into automatic control, namely automatically injecting boron and water with corresponding amount through the boron concentration value.
S2, cooling and depressurizing the main system to enable the temperature of the hot section of the main system to be lower than the first temperature and the pressure of the main system to be reduced to the first pressure;
in the cooling process, the cooling rate of the main system needs to be maintained to be lower than the basic rate, the water level of the voltage stabilizer is maintained at the zero load water level, and the temperature and the pressure of the main system are maintained within the limit values of a cooling and pressure reduction curve;
s3, locking safety injection signals, maintaining the stability of the parameter cooling process of the system, and ensuring that the temperature of a thermocouple at the outlet of the reactor core is reduced, the temperature of a hot section of a main system is reduced, and the supercooling degree of the outlet of the reactor core is increased;
and S4, adjusting the upper charging flow and the lower discharging flow of the pressure stabilizer, controlling the water level of the pressure stabilizer between the first range and the second range, and establishing the water level of the pressure stabilizer capable of accommodating the generation of the bubbles.
S5, cooling and depressurizing the main system to reduce the temperature of the hot section of the main system to a second temperature and reduce the pressure of the main system to a second pressure;
in the cooling process, maintaining the pressure of the main system at a first pressure, maintaining the cooling rate of the main system to be less than the first rate, and maintaining the temperature and the pressure of the main system within the limit value of a cooling and pressure reduction curve;
s6, cooling the main system to reduce the temperature of the hot section to a set temperature;
s7, adjusting the voltage stabilizer to make the charging flow rate equal to the discharging flow rate;
s8, reducing the pressure of the main system;
s9, monitoring the water level of the voltage stabilizer, and jumping to the step S10 when the water level of the voltage stabilizer is larger than a third range; when the water level of the voltage stabilizer is smaller than the third range, the step S11 is skipped to;
s10, putting an electric heater into the main system to boost the pressure of the main system and increase the pressure, and jumping to the step S8;
s11, obtaining a main system pressure, and if the main system pressure is higher than the set pressure, jumping to the step S8;
and S12, putting in a waste heat discharge system, and continuously cooling the main system to the cold shutdown working condition.
The operation of reducing the temperature and the pressure of the main system is realized by monitoring the water level of the voltage stabilizer and combining the pressure and the temperature in the main system.
The operation process of the invention does not need to add new systems and equipment in the nuclear power plant, and can utilize the existing related equipment of the nuclear power plant, and mainly comprises a temperature and pressure measuring device, a voltage stabilizer water level measuring device, a chemical and volume control system, a reactor boron and water supply system, a normal waste heat discharge system and other related control systems of the nuclear power plant.
First temperature, second temperature, first range, second range, third range, increase pressure, set temperature, set pressure, first pressure, second pressure, basic rate, first rate in this embodiment all can choose according to the circumstances of reality for use, under the circumstances of guaranteeing safety, reach the purpose of rapid cooling step down.
In addition, in this embodiment, there may be a situation that the difference between the second temperature and the set temperature is too large, and the pressure and the temperature in the reactor need to be maintained within the limits of the P-T diagram of the natural cycle, so that the difference between the second pressure and the set pressure may be too large, and therefore, if only the above steps are adopted, the temperature reduction range of S6 may be too large, and the pressure reduction range of S8 may be too large, so that a cooling fault occurs, and therefore, the single temperature reduction range is not too large, so an embodiment is provided below to implement stepped temperature reduction and pressure reduction.
Example two
In order to realize the stepwise temperature reduction and pressure reduction, steps S6-S11 in the first embodiment need to be repeated in a specific operation process, so that the temperature of the hot section of the main system is equal to the final temperature, and the pressure of the main system is equal to the final pressure.
A natural circulation cooling method for a nuclear power plant pressure vessel under the condition of liquid level indication failure comprises the following steps:
1. starting a cooling fan of a control rod driving mechanism, and boronating a main system to the boron concentration of a cooling reactor;
2. cooling and depressurizing the main system to make the temperature of the hot section of the main system lower than the first temperature and the pressure of the main system lower than the first pressure;
3. locking safety injection signals, maintaining the stability of a system parameter cooling process, and ensuring that the temperature of a thermocouple at the outlet of a reactor core is reduced, the temperature of a hot section of a main system is reduced, and the supercooling degree of the outlet of the reactor core is increased;
4. and adjusting the upper charging flow and the lower discharging flow of the pressure stabilizer, controlling the water level of the pressure stabilizer between the first range and the second range, and establishing the water level of the pressure stabilizer capable of accommodating the generation of bubbles.
5. Cooling and depressurizing the main system to reduce the temperature of the hot section of the main system to a second temperature and reduce the pressure of the main system to a second pressure;
6. cooling the main system to reduce the temperature of the hot section to a third temperature;
in the cooling process, maintaining the pressure of the main system at a second pressure, maintaining the cooling rate of the main system to be less than the second rate, and maintaining the temperature and the pressure of the main system within the limit value of a cooling and pressure reduction curve;
7. adjusting the voltage stabilizer to make the charging flow equal to the discharging flow;
8. reducing the pressure of the main system;
9. monitoring the water level of the voltage stabilizer, and jumping to the step 10 when the water level of the voltage stabilizer is larger than a third range; when the water level of the voltage stabilizer is smaller than the third measuring range, jumping to the step 11;
10. putting an electric heater into the system to boost the pressure of the main system and increase the pressure, and jumping to the step 8;
11. obtaining a main system pressure, and if the main system pressure is higher than the third pressure, skipping to the step 8; if the main system pressure is equal to the third pressure, jumping to step 12;
12. cooling the main system to reduce the temperature of the hot section to a fourth temperature;
maintaining the pressure of the main system at a third pressure, maintaining the cooling rate of the main system to be less than the third rate, and maintaining the temperature and the pressure of the main system within the limit values of a cooling and depressurizing curve;
13. adjusting the voltage stabilizer to make the charging flow equal to the discharging flow;
14. reducing the pressure of the main system;
15. monitoring the water level of the voltage stabilizer, and jumping to the step 16 when the water level of the voltage stabilizer is larger than a third range; when the water level of the voltage stabilizer is smaller than the third measuring range, jumping to the step 17;
16. putting an electric heater into the system to boost the pressure of the main system and increase the pressure, and jumping to the step 14;
17. obtaining a main system pressure, and if the main system pressure is higher than the fourth pressure, jumping to step 14; if the main system pressure is equal to the fourth pressure, jumping to step 18;
18. cooling the main system to reduce the temperature of the hot section to the final temperature;
and maintaining the pressure of the main system at the fourth pressure, maintaining the temperature reduction rate of the main system to be less than the fourth rate, and maintaining the temperature and the pressure of the main system to be within the limit values of the temperature reduction and pressure reduction curve.
19. Adjusting the voltage stabilizer to make the charging flow equal to the discharging flow;
20. reducing the pressure of the main system;
21. monitoring the water level of the voltage stabilizer, and jumping to the step 22 when the water level of the voltage stabilizer is larger than a third range; when the water level of the voltage stabilizer is smaller than the third measuring range, jumping to the step 23;
22. putting an electric heater into the system to boost the pressure of the main system and increase the pressure, and jumping to the step 20;
23. obtaining a main system pressure, and if the main system pressure is higher than the final pressure, jumping to the step 20; if the main system pressure is equal to the final pressure, go to step 24;
24. and (5) putting in a waste heat discharge system, and continuously cooling the main system to the cold shutdown working condition.
The first temperature, the second temperature, the third temperature, the fourth temperature, the first range, the second range, the third range, the pressure increase, the first pressure, the second pressure, the third pressure, the fourth pressure, the basic rate, the first rate, the second rate, the third rate, and the fourth rate in the embodiment can be selected according to actual conditions, and under the condition of ensuring safety, the purpose of quickly reducing temperature and pressure is achieved.
Meanwhile, in the embodiment, through setting the three stages of cooling of the steps 6 to 11, the steps 12 to 17 and the steps 18 to 23, the temperature is sequentially reduced to the third temperature, the fourth temperature and the final temperature, and the pressure is sequentially reduced to the third pressure, the fourth pressure and the final pressure, so that the stepped cooling is realized, and the cooling stability can be effectively increased.
Of course, if the temperature reduction range between the second temperature and the third temperature is still too large in this embodiment, steps S6 to S11 may be added before step 6 to reduce the temperature reduction range.
If the temperature reduction range between the third temperature and the fourth temperature is still too large in this embodiment, steps S6 to S11 may be added between step 11 and step 12 to reduce the temperature reduction range.
If the temperature reduction range between the fourth temperature and the final temperature is still too large in this embodiment, steps S6 to S11 may be added between step 17 and step 18 to reduce the temperature reduction range.
In summary, the temperature can be reduced by adding a step.
In order to prevent the coolant in the safety tank of the safety injection system (emergency core cooling system) from entering the main system when the internal pressure of the main system is reduced, after step 11 is completed, the safety tank needs to be isolated, and then step 12 is performed.
EXAMPLE III
The following provides a specific example which can realize a natural cooling operation of a pressurized water reactor.
In this embodiment, the first temperature is 284 ℃, the second temperature is 258 ℃, the third temperature is 230 ℃, the fourth temperature is 202 ℃, the final temperature is 177 ℃, the first pressure is 13.56mpa (a), the second pressure is 11.1mpa (a), the third pressure is 7.0mpa (a), the fourth pressure is 4.14mpa (a), the final pressure is 2.7mpa (a), the increased pressure is 0.7mpa (a), the first range is 12% range, the second range is 22% range, the third range is 86% range, the basic rate is 14 ℃/h, the first rate is 28 ℃/h, the second rate is 28 ℃/h, the third rate is 56 ℃/h, and the fourth rate is 56 ℃/h.
A natural circulation cooling method for a nuclear power plant pressure vessel under the condition of liquid level indication failure comprises the following steps:
1. starting a cooling fan of a control rod driving mechanism, and boronating a main system to the boron concentration of a cooling reactor;
2. and (3) reducing the temperature and the pressure of the main system to make the temperature of the hot section of the main system less than 284 ℃, and reducing the pressure of the main system to 13.56MPa (a), wherein the MPa (a) is expressed as absolute pressure.
In the cooling process, the cooling rate of the main system needs to be maintained to be less than 14 ℃/h, the water level of the voltage stabilizer needs to be maintained at a zero-load water level, the temperature and the pressure of the main system need to be maintained within the limits of a cooling and pressure reduction curve, and the narrow-range water level (34% -50%) of the steam generator needs to be maintained.
3. Locking safety injection signals, maintaining the stability of a system parameter cooling process, and ensuring that the temperature of a thermocouple at the outlet of a reactor core is reduced, the temperature of a hot section of a main system is reduced, and the supercooling degree of the outlet of the reactor core is increased; when the pressure of the voltage stabilizer rises to be more than 13.9MPa (a), the safety injection signal can automatically unlock.
4. And adjusting the upper charging flow and the lower discharging flow of the voltage stabilizer, controlling the water level of the voltage stabilizer between a 12% range and a 22% range, establishing the water level of the voltage stabilizer capable of accommodating the generation of bubbles, and reducing the water level of the voltage stabilizer can be executed only after the coolant in the voltage stabilizer reaches a saturated state.
5. Cooling and depressurizing the main system to reduce the temperature of a hot section of the main system to 258 ℃ and reduce the pressure of the main system to 11.1MPa (a);
in the cooling process, the pressure of the main system is maintained at 13.56MPa (a), the cooling rate of the main system is maintained to be less than 28 ℃/h, and the temperature and the pressure of the main system are maintained within the limit values of a cooling and pressure reduction curve;
6. cooling the main system to reduce the temperature of the hot section to 230 ℃;
in the cooling process, the pressure of the main system is maintained at 11.1MPa (a), the cooling rate of the main system is maintained to be less than 28 ℃/h, and the temperature and the pressure of the main system are maintained within the limit values of a cooling and pressure reduction curve;
7. adjusting the voltage stabilizer to make the charging flow equal to the discharging flow;
8. reducing the pressure of the main system;
9. monitoring the water level of the voltage stabilizer, and jumping to the step 10 when the water level of the voltage stabilizer is larger than 86% of the measuring range; when the water level of the voltage stabilizer is smaller than the 86% measuring range, jumping to the step 11;
10. putting an electric heater into the system, boosting the pressure of the main system by 0.7MPa (a), and jumping to the step 8;
11. obtaining the pressure of the main system, and if the pressure of the main system is higher than 7.0MPa (a), skipping to the step 8; if the pressure of the main system is equal to 7.0MPa (a), the step 12 is skipped to after the safety injection box is isolated;
12. cooling the main system to reduce the temperature of the hot section to 202 ℃;
maintaining the pressure of the main system at 7.0MPa (a), maintaining the cooling rate of the main system to be less than 56 ℃/h, and maintaining the temperature and the pressure of the main system to be within the limit values of a cooling and pressure reduction curve;
13. adjusting the voltage stabilizer to make the charging flow equal to the discharging flow;
14. reducing the pressure of the main system;
15. monitoring the water level of the voltage stabilizer, and jumping to the step 16 when the water level of the voltage stabilizer is larger than 86% of the measuring range; when the water level of the voltage stabilizer is smaller than the 86% measuring range, jumping to the step 17;
16. putting an electric heater into the system, boosting the pressure of the main system by 0.7MPa (a), and jumping to the step 14;
17. obtaining a main system pressure, and if the main system pressure is higher than 4.14MPa (a), skipping to step 14; if the master system pressure is equal to 4.14MPa (a), jumping to step 18;
18. cooling the main system to reduce the temperature of the hot section to 177 ℃;
maintaining the pressure of the main system at 4.14MPa (a), maintaining the cooling rate of the main system to be less than 56 ℃/h, and maintaining the temperature and the pressure of the main system to be within the limits of a cooling and pressure reduction curve.
19. Adjusting the voltage stabilizer to make the charging flow equal to the discharging flow;
20. reducing the pressure of the main system;
21. monitoring the water level of the voltage stabilizer, and jumping to step 22 when the water level of the voltage stabilizer is larger than 86% of the range; when the water level of the voltage stabilizer is smaller than the 86% measuring range, jumping to the step 23;
22. putting an electric heater into the system, boosting the pressure of the main system by 0.7MPa (a), and jumping to the step 20;
23. obtaining a main system pressure, and if the main system pressure is higher than 2.7MPa (a), skipping to the step 20; if the main system pressure is equal to 2.7MPa (a), jumping to step 24;
24. and (5) putting in a waste heat discharge system, and continuously cooling the main system to the cold shutdown working condition.
In addition, in this embodiment, the main system performs depressurization through the auxiliary spraying system, and if the auxiliary spraying system is not available, the pressure regulator safety valve is used for depressurization.
Lowering the voltage regulator water level may only be performed after the coolant within the voltage regulator reaches a saturated state.
In addition, the water level of the voltage stabilizer in the embodiment can be adjusted manually.
Based on the above, the embodiment of the invention provides a natural circulation cooling method under the condition that the liquid level indication of the pressure vessel of the nuclear power plant fails, which can effectively avoid the steam generation of an upper end enclosure or reduce the steam generation amount in the cooling process under the condition that the liquid level information of the pressure vessel is lost, prevent the interruption of natural circulation cooling and ensure that the nuclear power plant is guided to a safe and controllable cold shutdown state under the accident.
The flash evaporation steam production or the gas production reduction of pressure vessel upper cover in the natural circulation cooling in-process under the condition that pressure vessel liquid level indication became invalid can be effectively avoided, the risk of natural circulation cooling termination has been eliminated, can be with the nuclear power plant of guide to safe controllable cold shut down state, ensured nuclear power plant's safety.
In the description herein, reference to the description of the terms "one embodiment/mode," "some embodiments/modes," "example," "specific example," or "some examples," etc., means that a particular feature, structure, material, or characteristic described in connection with the embodiment/mode or example is included in at least one embodiment/mode or example of the application. In this specification, the schematic representations of the terms used above are not necessarily intended to be the same embodiment/mode or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments/modes or examples. Furthermore, the various embodiments/aspects or examples and features of the various embodiments/aspects or examples described in this specification can be combined and combined by one skilled in the art without conflicting therewith.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one such feature. In the description of the present application, "plurality" means at least two, e.g., two, three, etc., unless specifically limited otherwise.
It will be understood by those skilled in the art that the foregoing embodiments are merely for clarity of description and are not intended to limit the scope of the invention. It will be apparent to those skilled in the art that other variations or modifications may be made on the above invention and still be within the scope of the invention.
Claims (10)
1. A natural circulation cooling method under the condition of liquid level indication failure of a pressure vessel of a nuclear power plant is characterized by comprising the following steps:
s1, starting a cooling fan of the control rod driving mechanism, and boronizing the main system to the boron concentration of the cooling reactor;
s2, cooling and depressurizing the main system to enable the temperature of the hot section of the main system to be lower than the first temperature and the pressure of the main system to be reduced to the first pressure;
s3, locking safety injection signals, maintaining the stability of the parameter cooling process of the system, and ensuring that the temperature of a thermocouple at the outlet of the reactor core is reduced, the temperature of a hot section of a main system is reduced, and the supercooling degree of the outlet of the reactor core is increased;
s4, adjusting the upper charging flow and the lower discharging flow of the voltage stabilizer, and controlling the water level of the voltage stabilizer between a first range and a second range;
s5, cooling and depressurizing the main system to reduce the temperature of the hot section of the main system to a second temperature and reduce the pressure of the main system to a second pressure;
s6, cooling the main system to reduce the temperature of the hot section to a set temperature;
s7, adjusting the voltage stabilizer to make the charging flow rate equal to the discharging flow rate;
s8, reducing the pressure of the main system;
s9, monitoring the water level of the voltage stabilizer, and jumping to the step S10 when the water level of the voltage stabilizer is larger than a third range; when the water level of the voltage stabilizer is smaller than the third range, the step S11 is skipped to;
s10, putting an electric heater into the main system to boost the pressure of the main system and increase the pressure, and jumping to the step S8;
s11, obtaining a main system pressure, and if the main system pressure is higher than the set pressure, jumping to the step S8;
and S12, putting in a waste heat discharge system, and continuously cooling the main system to the cold shutdown working condition.
2. The method of claim 1, wherein the steps S6-S11 are repeated to make the main system hot leg temperature equal to the final temperature and the main system pressure equal to the final pressure.
3. The natural circulation cooling method for nuclear power plant pressure vessel liquid level indication failure as claimed in claim 2, wherein the steps S6-S11 are repeated, and the method specifically comprises the following steps:
a1, cooling the main system to reduce the temperature of the hot section to a third temperature;
a2, adjusting the voltage stabilizer to make the upper charging flow equal to the lower discharging flow;
a3, reducing the pressure of the main system;
a4, monitoring the water level of the voltage stabilizer, and jumping to the step A5 when the water level of the voltage stabilizer is larger than a third range; when the water level of the voltage stabilizer is smaller than the third range, the step A6 is skipped to;
a5, putting an electric heater into the main system to boost the pressure of the main system and increase the pressure, and jumping to the step A3;
a6, acquiring a main system pressure, and jumping to the step A3 if the main system pressure is higher than the third pressure; if the main system pressure is equal to the third pressure, then go to step A7;
a7, cooling the main system to reduce the temperature of the hot section to a fourth temperature;
a8, adjusting the voltage stabilizer to make the upper charging flow equal to the lower discharging flow;
a9, reducing the pressure of the main system;
a10, monitoring the water level of the voltage stabilizer, and jumping to the step A11 when the water level of the voltage stabilizer is larger than a third range; when the water level of the voltage stabilizer is smaller than the third range, the step A12 is skipped to;
a11, putting an electric heater into the main system to boost the pressure of the main system and increase the pressure, and jumping to the step A9;
a12, obtaining a main system pressure, and jumping to the step A9 if the main system pressure is higher than the fourth pressure; if the main system pressure is equal to the fourth pressure, go to step A13;
a13, cooling the main system to reduce the temperature of the hot section to the final temperature;
a14, adjusting the voltage stabilizer to make the upper charging flow equal to the lower discharging flow;
a15, reducing the pressure of the main system;
a16, monitoring the water level of the voltage stabilizer, and jumping to the step A17 when the water level of the voltage stabilizer is larger than a third range; when the water level of the voltage stabilizer is smaller than the third range, the step A18 is skipped to;
a17, putting an electric heater into the main system to boost the pressure of the main system and increase the pressure, and jumping to the step A15;
a18, obtaining a main system pressure, and if the main system pressure is higher than the final pressure, jumping to the step A15; if the main system pressure is equal to the final pressure, go to step A19;
and A19, putting in a waste heat discharge system, and continuously cooling the main system to the cold shutdown working condition.
4. The natural circulation cooling method under the condition of the liquid level indication failure of the nuclear power plant pressure vessel as claimed in claim 3, wherein in the cooling process of the step S2, the cooling rate of the main system is maintained to be smaller than the basic rate, the water level of the voltage stabilizer is maintained at the zero load water level, and the temperature and the pressure of the main system are maintained within the limits of the cooling and pressure reduction curve;
in the cooling process of step S5, the main system pressure is maintained at the first pressure, the main system cooling rate is maintained to be less than the first rate, and the main system temperature and pressure are maintained within the cooling and pressure reduction curve limits.
5. The method of claim 4, wherein during the cooling of step A1, the main system pressure is maintained at the second pressure, the main system cooling rate is maintained at a rate less than the second rate, and the main system temperature and pressure are maintained within the limits of the reduced temperature/pressure curve.
6. The method of claim 5, wherein during the cooling of step A7, the main system pressure is maintained at the third pressure, the main system cooling rate is maintained at a rate less than the third rate, and the main system temperature and pressure are maintained within limits of a reduced temperature/pressure curve.
7. The method of claim 6, wherein during the cooling of step A13, the main system pressure is maintained at a fourth pressure, the main system cooling rate is maintained at a rate less than the fourth rate, and the main system temperature and pressure are maintained within limits of a reduced temperature/pressure curve.
8. The method of claim 7, wherein the step A7 is performed after the step A6 is completed and the safety injection tank needs to be isolated.
9. The method of claim 7, wherein the nuclear power plant pressure vessel level indicator fails natural circulation cooling. The first temperature is 284 ℃, the second temperature is 258 ℃, the third temperature is 230 ℃, the fourth temperature is 202 ℃, the final temperature is 177 ℃, the first pressure is 13.56mpa (a), the second pressure is 11.1mpa (a), the third pressure is 7.0mpa (a), the fourth pressure is 4.14mpa (a), the final pressure is 2.7mpa (a), the incremental pressure is 0.7mpa (a), the first range is 12% range, the second range is 22% range, the third range is 86% range, the base rate is 14 ℃/h, the first rate is 28 ℃/h, the second rate is 28 ℃/h, the third rate is 56 ℃/h, and the fourth rate is 56 ℃/h.
10. A method of cooling a pressurized water reactor nuclear power plant, comprising the steps of:
triggering reactor shutdown in case of a reactor accident;
step two, if the main system main pump fails to start, natural circulation cooling is executed;
step three, if the pressure vessel liquid level indication fails, executing the natural circulation cooling method under the condition of the failure of the liquid level indication of the nuclear power plant pressure vessel according to any one of claims 1 to 9.
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